Standard Review Plan for 

Conventional Uranium Mill 

and Heap Leach Facilities

Draft Report for Comment

Office of Nuclear Material Safety and Safeguards

NUREG-2126
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Standard Review Plan for 

Conventional Uranium Mill 

and Heap Leach Facilities

Draft Report for Comment

Manuscript Completed: May 2014

Date Published: November 2014

Douglas T. Mandeville, NRC Project Manager

Office of Nuclear Material Safety and Safeguards

NUREG-2126

 
COMMENTS ON DRAFT REPORT

Any interested party may submit comments on this report for consideration by the NRC staff. 

Comments may be accompanied by additional relevant information or supporting data. Please 

specify the report number NUREG-2126 in your comments, and send them by the end of the 

comment period specified in the Federal Register notice announcing the availability of this 

report. 

Addresses: You may submit comments by any one of the following methods. Please include 

Docket ID NRC-2014-0178 in the subject line of your comments. Comments submitted in 

writing or in electronic form will be posted on the NRC website and on the Federal rulemaking 

website http://www.regulations.gov. 

Federal Rulemaking Website: Go to http://www.regulations.gov and search for documents 

filed under Docket ID NRC-2014-0178. Address questions about NRC dockets to Carol 

Gallagher at 301-287-3422 or by e-mail at Carol.Gallagher@nrc.gov.

Mail comments to: Cindy Bladey, Chief, Rules, Announcements, and Directives Branch

(RADB), Division of Administrative Services, Office of Administration, Mail Stop: 

3WFN-06-A44MP, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.

For any questions about the material in this report, please contact: Douglas T. Mandeville, 

Project Manager, at 301-415-0724 or by e-mail at douglas.mandeville@nrc.gov.

Please be aware that any comments that you submit to the NRC will be considered a public 

record and entered into the Agencywide Documents Access and Management System 

(ADAMS). Do not provide information you would not want to be publicly available.
iii

1 ABSTRACT

2 A U.S. Nuclear Regulatory Commission source and byproduct materials license is 

3 required under the provisions of Title 10 of the U.S. Code of Federal Regulations, Part 40

4 (10 CFR Part 40), “Domestic Licensing of Source Material,” for the operation of a uranium mill 

5 and the disposal of ‘tailings,” wastes produced by the extraction of concentration of source 

6 material from ores processed primarily for their source material content. Appendix A to Part 40 

7 establishes technical and other criteria related to siting, operation, decontamination, 

8 decommissioning, and reclamation of mills and tailings at mill sites. An applicant for a new 

9 license, or for the renewal or amendment of an existing license, is required to provide detailed 

10 information on the facilities, equipment, and procedures used and an environmental report that 

11 discusses the effects of proposed operations on the health and safety of the public and on 

12 the environment.

13 The standard review plan is prepared for the guidance of staff reviewers, in the Office of Nuclear 

14 Material Safety and Safeguards, in performing safety reviews of applications to develop and 

15 operate conventional uranium mills or heap leach facilities. It provides guidance for new license 

16 applications, renewals, and amendments. The principal purpose of the standard review plan is 

17 to assure the quality and uniformity of staff reviews and to present a well-defined base from 

18 which to evaluate changes in the scope and requirements of a review.

19 The standard review plan is written to cover a variety of site conditions and facility designs. 

20 Each section is written to provide a description of the areas of review, review procedures, 

21 acceptance criteria, and evaluation findings. However, for a given application, the staff 

22 reviewers may select and emphasize particular aspects of each standard review plan section, 

23 as appropriate for the application.

24 Paperwork Reduction Act Statement 

25 The information collections contained in the Standard Review Plan are covered by the 

26 requirements of 10 CFR Part 20 and 10 CFR Part 40, and were approved by the Office of 

27 Management and Budget, approval numbers 3150-0014 and 3150-0020.

28 Public Protection Notification

29 The NRC may not conduct or sponsor, and a person is not required to respond to, a request for 

30 information or an information collection requirement unless the requesting document displays a 

31 currently valid OMB control number.

v

1 CONTENTS

2 Section Page

3

4 ABSTRACT................................................................................................................................ iii

5 EXECUTIVE SUMMARY ...........................................................................................................xi

6

7 1.0 PROPOSED ACTIVITIES.............................................................................................1-1

8 1.1 Areas of Review................................................................................................1-1

9 1.2 Review Procedure.............................................................................................1-1

10 1.3 Acceptance Criterion.........................................................................................1-1

11 1.4 Evaluation Findings...........................................................................................1-2

12 1.5 References .......................................................................................................1-3

13

14 2.0 SITE CHARACTERIZATION ........................................................................................2-1

15 2.1 Site Location and Layout...................................................................................2-1

16 2.1.1 Areas of Review ....................................................................................2-1

17 2.1.2 Review Procedures ...............................................................................2-1

18 2.1.3 Acceptance Criteria ...............................................................................2-2

19 2.1.4 Evaluation Findings ...............................................................................2-3

20 2.1.5 Reference..............................................................................................2-4

21 2.2 Historical Investigations ....................................................................................2-4

22 2.2.1 Areas of Review ....................................................................................2-4

23 2.2.2 Review Procedures ...............................................................................2-5

24 2.2.3 Acceptance Criteria ...............................................................................2-5

25 2.2.4 Evaluation Findings ...............................................................................2-5

26 2.2.5 References............................................................................................2-6

27 2.3 Meteorology......................................................................................................2-6

28 2.3.1 Areas of Review ....................................................................................2-6

29 2.3.2 Review Procedures ...............................................................................2-7

30 2.3.3 Acceptance Criteria ...............................................................................2-7

31 2.3.4 Evaluation Findings ...............................................................................2-9

32 2.3.5 References..........................................................................................2-10

33 2.4 Geology and Seismology ................................................................................2-10

34 2.4.1 Areas of Review ..................................................................................2-10

35 2.4.2 Review Procedures .............................................................................2-11

36 2.4.3 Acceptance Criteria .............................................................................2-12

37 2.4.4 Evaluation Findings .............................................................................2-14

38 2.4.5 Reference............................................................................................2-15

39 2.5 Soil .................................................................................................................2-15

40 2.5.1 Areas of Review ..................................................................................2-15

41 2.5.2 Review Procedures .............................................................................2-15

42 2.5.3 Acceptance Criteria .............................................................................2-16

43 2.5.4 Evaluation Findings .............................................................................2-17

44 2.5.5 Reference............................................................................................2-17

45 2.6 Geotechnical...................................................................................................2-18

46 2.6.1 Areas of Review ..................................................................................2-18

47 2.6.2 Review Procedures .............................................................................2-18

48
vi

1 CONTENTS (Continued)

2 Section Page

3

4 2.6.3 Acceptance Criteria .............................................................................2-19

5 2.6.4 Evaluation Findings .............................................................................2-20

6 2.6.5 References..........................................................................................2-21

7 2.7 Hydrology .......................................................................................................2-21

8 2.7.1 Groundwater Hydrology—Regional and Site Specific..........................2-21

9 2.7.1.1 Areas of Review....................................................................2-21

10 2.7.1.2 Review Procedures...............................................................2-22

11 2.7.1.3 Acceptance Criteria...............................................................2-23

12 2.7.1.4 Evaluation Findings...............................................................2-27

13 2.7.1.5 References ...........................................................................2-28

14 2.7.2 Surface Water Hydrology—Regional and Site Specific........................2-28

15 2.7.2.1 Areas of Review....................................................................2-28

16 2.7.2.2 Review Procedures...............................................................2-29

17 2.7.2.3 Acceptance Criteria...............................................................2-29

18 2.7.2.4 Evaluation Findings...............................................................2-31

19 2.7.2.5 References ...........................................................................2-32

20 2.8 Preoperational Monitoring...............................................................................2-33

21 2.8.1 Radiological Preoperational Monitoring ...............................................2-33

22 2.8.1.1 Areas of Review....................................................................2-33

23 2.8.1.2 Review Procedures...............................................................2-33

24 2.8.1.3 Acceptance Criteria...............................................................2-33

25 2.8.1.4 Evaluation Findings...............................................................2-36

26 2.8.1.5 Reference .............................................................................2-37

27 2.8.2 Nonradiological Preoperational Monitoring ..........................................2-37

28 2.8.2.1 Areas of Review....................................................................2-37

29 2.8.2.2 Review Procedures...............................................................2-37

30 2.8.2.3 Acceptance Criteria...............................................................2-38

31 2.8.2.4 Evaluation Findings...............................................................2-39

32 2.8.2.5 Reference .............................................................................2-40

33

34 3.0 DESCRIPTION AND DESIGN OF PROPOSED FACILITY...........................................3-1

35 3.1 Conventional Uranium Mill Facilities..................................................................3-1

36 3.1.1 Areas of Review ....................................................................................3-1

37 3.1.2 Review Procedures ...............................................................................3-1

38 3.1.3 Acceptance Criteria ...............................................................................3-1

39 3.1.4 Evaluation Findings ...............................................................................3-2

40 3.1.5 References............................................................................................3-3

41 3.2 Heap Leach Facilities........................................................................................3-3

42 3.2.1 Areas of Review ....................................................................................3-3

43 3.2.2 Review Procedures ...............................................................................3-4

44 3.2.3 Acceptance Criteria ...............................................................................3-4

45 3.2.4 Evaluation Findings ...............................................................................3-5

46 3.2.5 References............................................................................................3-6

47 3.3 Design of Surface Impoundments .....................................................................3-6

48 3.3.1 Areas of Review ....................................................................................3-6

49 3.3.2 Review Procedures ...............................................................................3-7

50 3.3.3 Acceptance Criteria .............................................................................3-13
vii

1 CONTENTS (Continued)

2 Section Page

3

4 3.3.4 Evaluation Findings .............................................................................3-30

5 3.3.5 References..........................................................................................3-32

6 3.4 Uranium Recovery Process ............................................................................3-39

7 3.4.1 Areas of Review ..................................................................................3-39

8 3.4.2 Review Procedures .............................................................................3-39

9 3.4.3 Acceptance Criteria .............................................................................3-40

10 3.4.4 Evaluation Findings .............................................................................3-41

11 3.4.5 References..........................................................................................3-42

12 3.5 Waste Management........................................................................................3-42

13 3.5.1 Areas of Review ..................................................................................3-42

14 3.5.2 Review Procedures .............................................................................3-43

15 3.5.3 Acceptance Criteria .............................................................................3-44

16 3.5.4 Evaluation Findings .............................................................................3-49

17 3.5.5 References..........................................................................................3-51

18

19 4.0 MANAGEMENT............................................................................................................4-1

20 4.1 Corporate Organization and Administrative Procedures....................................4-1

21 4.1.1 Areas of Review ....................................................................................4-1

22 4.1.2 Review Procedures ...............................................................................4-1

23 4.1.3 Acceptance Criteria ...............................................................................4-2

24 4.1.4 Evaluation Findings ...............................................................................4-3

25 4.1.5 References............................................................................................4-4

26 4.2 Management Control Program..........................................................................4-4

27 4.2.1 Areas of Review ....................................................................................4-4

28 4.2.2 Review Procedures ...............................................................................4-5

29 4.2.3 Acceptance Criteria ...............................................................................4-6

30 4.2.4 Evaluation Findings ...............................................................................4-9

31 4.2.5 References..........................................................................................4-10

32 4.3 Management Audit and Inspection Program ...................................................4-11

33 4.3.1 Areas of Review ..................................................................................4-11

34 4.3.2 Review Procedure ...............................................................................4-11

35 4.3.3 Acceptance Criterion ...........................................................................4-11

36 4.3.4 Evaluation Findings .............................................................................4-12

37 4.3.5 References..........................................................................................4-13

38 4.4 Qualifications for Personnel Conducting the Radiation Safety Program ..........4-13

39 4.4.1 Areas of Review ..................................................................................4-13

40 4.4.2 Review Procedure ...............................................................................4-13

41 4.4.3 Acceptance Criterion ...........................................................................4-13

42 4.4.4 Evaluation Findings .............................................................................4-13

43 4.4.5 Reference............................................................................................4-14

44 4.5 Radiation Safety Training................................................................................4-14

45 4.5.1 Areas of Review ..................................................................................4-14

46 4.5.2 Review Procedure ...............................................................................4-15

47 4.5.3 Acceptance Criterion ...........................................................................4-15

48 4.5.4 Evaluation Findings .............................................................................4-15

49 4.5.5 References..........................................................................................4-16
viii

1 CONTENTS (Continued)

2 Section Page

3

4 4.6 Security...........................................................................................................4-16

5 4.6.1 Areas of Review ..................................................................................4-16

6 4.6.2 Review Procedure ...............................................................................4-17

7 4.6.3 Acceptance Criterion ...........................................................................4-17

8 4.6.4 Evaluation Findings .............................................................................4-17

9 4.6.5 References..........................................................................................4-18

10 4.7 Quality Assurance...........................................................................................4-18

11 4.7.1 Areas of Review ..................................................................................4-18

12 4.7.2 Review Procedures .............................................................................4-18

13 4.7.3 Acceptance Criteria .............................................................................4-18

14 4.7.4 Evaluation Findings .............................................................................4-20

15 4.7.5 References..........................................................................................4-20

16

17 5.0 OPERATIONAL ENVIRONMENTAL MONITORING.....................................................5-1

18 5.1 Operational Environmental Monitoring—Surface Water ....................................5-1

19 5.1.1 Areas of Review ....................................................................................5-1

20 5.1.2 Review Procedures ...............................................................................5-1

21 5.1.3 Acceptance Criteria ...............................................................................5-1

22 5.1.4 Evaluation Findings ...............................................................................5-2

23 5.1.5 References............................................................................................5-3

24 5.2 Operational Environmental Monitoring—Groundwater ......................................5-3

25 5.2.1 Areas of Review ....................................................................................5-3

26 5.2.2 Review Procedures ...............................................................................5-5

27 5.2.3 Acceptance Criteria ...............................................................................5-6

28 5.2.4 Evaluation Findings ...............................................................................5-9

29 5.2.5 References..........................................................................................5-10

30 5.3 Operational Airborne Monitoring .....................................................................5-11

31 5.3.1 Areas of Review ..................................................................................5-11

32 5.3.2 Review Procedures .............................................................................5-11

33 5.3.3 Acceptance Criteria.............................................................................5-12

34 5.3.4 Evaluation Findings .............................................................................5-13

35 5.3.5 References..........................................................................................5-14

36 5.4 Other Operational Monitoring..........................................................................5-14

37 5.4.1 Areas of Review ..................................................................................5-14

38 5.4.2 Review Procedures .............................................................................5-15

39 5.4.3 Acceptance Criteria .............................................................................5-15

40 5.4.4 Evaluation Findings .............................................................................5-16

41 5.4.5 Reference............................................................................................5-17

42

43 6.0 RADIATION SAFETY CONTROLS AND MONITORING ..............................................6-1

44 6.1 External Radiation Exposure Monitoring Program.............................................6-1

45 6.1.1 Areas of Review ....................................................................................6-1

46 6.1.2 Review Procedures ...............................................................................6-1

47 6.1.3 Acceptance Criteria ...............................................................................6-2

48 6.1.4 Evaluation Findings ...............................................................................6-3

49 6.1.5 References............................................................................................6-4

50
ix

1 CONTENTS (Continued)

2 Section Page

3

4 6.2 Airborne Radioactivity Monitoring Program .......................................................6-4

5 6.2.1 Areas of Review ....................................................................................6-4

6 6.2.2 Review Procedures ...............................................................................6-5

7 6.2.3 Acceptance Criteria ...............................................................................6-6

8 6.2.4 Evaluation Findings ...............................................................................6-8

9 6.2.5 References............................................................................................6-9

10 6.3 Exposure Calculations ....................................................................................6-10

11 6.3.1 Areas of Review ..................................................................................6-10

12 6.3.2 Review Procedures .............................................................................6-10

13 6.3.3 Acceptance Criteria .............................................................................6-11

14 6.3.4 Evaluation Findings .............................................................................6-12

15 6.3.5 References..........................................................................................6-13

16 6.4 Bioassay Program...........................................................................................6-13

17 6.4.1 Areas of Review ..................................................................................6-13

18 6.4.2 Review Procedures .............................................................................6-14

19 6.4.3 Acceptance Criteria .............................................................................6-14

20 6.4.4 Evaluation Findings .............................................................................6-15

21 6.4.5 References..........................................................................................6-16

22 6.5 Contamination Control Program......................................................................6-16

23 6.5.1 Areas of Review ..................................................................................6-16

24 6.5.2 Review Procedures .............................................................................6-17

25 6.5.3 Acceptance Criteria .............................................................................6-18

26 6.5.4 Evaluation Findings .............................................................................6-19

27 6.5.5 References..........................................................................................6-20

28

29 7.0 RECLAMATION AND DECOMMISSIONING PLAN......................................................7-1

30 7.1.1 Acceptance Criteria...........................................................................................7-3

31 7.1.2 Evaluation Findings...........................................................................................7-4

32 7.1.3 Reference .........................................................................................................7-5

33

34 8.0 ACCIDENTS.................................................................................................................8-1

35 8.1 Accidents Involving Radioactivity ......................................................................8-1

36 8.1.1 Areas of Review ....................................................................................8-1

37 8.1.2 Review Procedures ...............................................................................8-1

38 8.1.3 Acceptance Criteria ...............................................................................8-2

39 8.1.4 Evaluation Findings ...............................................................................8-2

40 8.1.5 Reference..............................................................................................8-3

41 8.2 Transportation Accidents ..................................................................................8-3

42 8.2.1 Areas of Review ....................................................................................8-3

43 8.2.2 Review Procedures ...............................................................................8-3

44 8.2.3 Acceptance Criteria ...............................................................................8-4

45 8.2.4 Evaluation Findings ...............................................................................8-4

46 8.2.5 References............................................................................................8-5

47 8.3 Nonradiological Accidents.................................................................................8-5

48 8.3.1 Areas of Review ....................................................................................8-5

49 8.3.2 Review Procedures ...............................................................................8-5

50 8.3.3 Acceptance Criteria ...............................................................................8-6
x

1 CONTENTS (Continued)

2 Section Page

3

4 8.3.4 Evaluation Findings ...............................................................................8-6

5 8.3.5 References............................................................................................8-7

6

7 APPENDICES

8

9 A GUIDANCE FOR REVIEWING HISTORICAL ASPECTS OF SITE 

10 PERFORMANCE FOR LICENSE RENEWALS AND AMENDMENTS.........................A-1

11 B RELATIONSHIP OF 10 CFR PART 40, APPENDIX A, REQUIREMENTS TO 

12 STANDARD REVIEW PLAN SECTIONS ....................................................................B-1

13 C GUIDANCE TO THE U.S. NUCLEAR REGULATORY COMMISSION STAFF 

14 ON THE RADIUM BENCHMARK DOSE APPROACH ................................................C-1

15 D GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT 

16 PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF 

17 LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL ......D-1

18 E OUTLINE RECOMMENDED BY THE U.S. NUCLEAR REGULATORY 

19 COMMISSION STAFF FOR PREPARING SITE-SPECIFIC FACILITY 

20 RECLAMATION AND STABILIZATION COST ESTIMATES FOR REVIEW................E-1

21 F U.S. NUCLEAR REGULATORY COMMISSION POLICY OF SAFETY

22 CULTURE ................................................................................................................... F-1

23

24

25
xi

1 EXECUTIVE SUMMARY

2 This standard review plan (SRP) has been developed to assist U.S. Nuclear Regulatory 

3 Commission (NRC) staff in performing safety reviews of license applications associated with 

4 uranium recovery operations using conventional uranium milling or heap leach techniques. 

5 Both techniques extract and concentrate uranium from mined ore to create a product that is 

6 commonly referred to as “yellowcake,” which is used for making fuel for nuclear reactors.

7

8 The NRC has the authority to regulate uranium milling under the Atomic Energy Act of 1954, 

9 as amended, and the Uranium Mill Tailings Radiation Control Act of 1978, as amended. 

10 Uranium recovery is any activity that produces byproduct material, which is defined as “the 

11 tailings or wastes produced by the extraction or concentration of uranium or thorium from any 

12 ore processed primarily for its source material content.” Most byproduct material from 

13 conventional uranium mills and heap leach facilities is mill tailings. Other wastes, such as 

14 contaminated equipment, are also byproduct material. NRC does not regulate the mining of 

15 uranium. The U.S. Department of Interior Office of Surface Mining, the U.S. Department 

16 of Labor Mine Safety and Health Administration, and the individual states regulate 

17 mining operations.

18

19 An NRC source and byproduct material license is required under the provisions of 

20 10 CFR Part 40 to recover uranium from ore (physical and/or chemical processes). General 

21 provisions for issuance, amendment, transfer, and renewal of NRC licenses are contained in 

22 10 CFR Part 2 and 10 CFR 40.31. An applicant for a new operating license for a facility is 

23 required to provide detailed information on the facility, equipment, and procedures it plans to 

24 use in a technical report that also discusses the effects of proposed operations on public health 

25 and safety. For license renewals and amendments, the licensee’s (hereafter referred to as an 

26 applicant) focus should be on changes in proposed operations that NRC has not previously 

27 reviewed. Also for license renewals, the applicant needs to present operational history since 

28 the last license issuance. The technical report will serve as a basis for a detailed review by 

29 NRC staff to determine whether the proposed activities will protect public health and safety and 

30 whether the applicant has addressed the applicable NRC regulations in 10 CFR Part 20; 

31 10 CFR Part 40 and 10 CFR Part 40, Appendix A.

32

33 This SRP provides guidance for the detailed safety (technical) review of new and renewal 

34 license applications and amendment requests associated with conventional uranium mills and 

35 heap leach facilities. The staff will use information in this SRP in the review of applications for 

36 new facilities, renewals, and amendments. Reference to guidance and licensing documents in 

37 this SRP will refer to the most current version of that document. In any application, it is the 

38 responsibility of the reviewer, as well as the applicant, to use the most current update that may 

39 occur following publication of this SRP. Throughout this SRP and accompanying appendices, 

40 “application” is synonymous with new, renewal, or amendment license applications, and 

41 “applicant” is synonymous with new applicant or licensee.

42

43 An applicant must clearly demonstrate the manner in which the requirements and objectives in 

44 applicable sections of 10 CFR Part 20 and 10 CFR Part 40 have been addressed, as well as 

45 NRC regulations in 10 CFR Part 51 implementing the National Environmental Policy Act of 

46 1969, as amended (NEPA). Guidance for addressing NEPA requirements for the licensing of 

47 uranium recovery operations is contained in NUREG–1748, Environmental Review Guidance for 

48 Licensing Actions Associated with NMSS Programs (NRC, 2003).

49
Executive Summary

xii

1 Use of the SRP enables consistent quality and uniformity in NRC staff reviews. Each section in 

2 this SRP provides guidance on areas of review, review procedures, acceptance criteria, and 

3 evaluation findings. The subsection on areas of review describes what should be reviewed. 

4 The subsection on review procedures lists how the staff review is to be accomplished. The 

5 subsection on acceptance criteria lists what is acceptable in a demonstration of compliance with 

6 the regulations. The subsection on evaluation findings outlines a procedure for reporting the 

7 NRC staff evaluation whether compliance with the applicable sections in Title 10 of the 

8 U.S. Code of Federal Regulations has been met. In the license application review, the NRC 

9 staff must determine whether operations will be conducted in an acceptable manner and in 

10 compliance with applicable regulations.

11

12 The detailed review procedures and acceptance criteria contained in this standard review plan 

13 are intended to provide guidance on the review of applications for conventional uranium mills or 

14 heap leach facilities and assist NRC staff in making the necessary findings in an effective and 

15 efficient manner. If information is not contained in an application in accordance with a section of 

16 this SRP, then the applicant should describe why the information is not necessary or 

17 appropriate. The NRC staff has the responsibility to conduct an evaluation of the public health 

18 and safety aspects of an applicant’s proposed program. Some sections of this SRP may not be 

19 appropriate or necessary for a detailed review because of site-specific characteristics or other 

20 circumstances. However, if the NRC staff determines that an application is incomplete, then 

21 delays in processing the application may occur or the application may be rejected.

22

23 This SRP is intended to cover only those aspects of the NRC regulatory mission related to the 

24 licensing of conventional uranium mills or heap leach facilities. Uranium ore removed from a 

25 mine and transported directly to a conventional mill or heap leach facility would be subject to 

26 NRC jurisdiction when it crosses the license boundary. This is consistent with of 10 CFR Part 

27 40, Appendix A, Criterion 5H, which requires that steps be taken to minimize penetration of 

28 radionuclides into underlying soils at uranium ore stockpile locations. The initiation of NRC 

29 jurisdiction for other scenarios where uranium ore is altered after removal from its place in 

30 nature prior to transport to a conventional mill or heap leach facility would be handled on a 

31 case by case basis. This evaluation depends on proposed operating characteristics of 

32 individual facilities. 

33

34 This SRP focuses on review guidance for the applicant’s technical report accompanying license 

35 applications and amendments to determine whether the proposed activities will protect public 

36 health and safety. The product documenting the staff review of the applicant’s technical report 

37 is a safety evaluation report (SER) or technical evaluation report (TER), depending on the 

38 licensing action. As such, the SRP helps focus the staff review on determining whether a facility 

39 can be constructed and operated in compliance with the applicable NRC regulations. This SRP 

40 is also intended to make information about the regulatory review process widely available and to 

41 improve communication and understanding of the staff review process by interested members 

42 of the public and the uranium recovery industry.

43

44 The acceptance criteria presented in this SRP are for the guidance of the NRC staff responsible 

45 for the review of applications to operate conventional uranium mills and heap leach facilities. 

46 Review plans are not substitutes for the NRC’s regulations, and compliance with a particular 

47 SRP is not required. This SRP describes acceptable methodologies for demonstrating 

48 regulatory compliance. Methods and solutions different from those set out in the SRP will be 

49 acceptable if the applicant provides an adequate basis for the findings necessary for the 

50 issuance or continuance of a license by NRC.

51
Executive Summary

xiii

1 For license application amendments and renewals, the review should focus on the changes 

2 proposed in the application and, if applicable, operational and inspection history since the prior 

3 license was issued or renewed. In addition, the applicant should discuss the likely 

4 consequences of any health and safety impacts of the proposed activities. Staff should use the 

5 appropriate sections of this document when reviewing amendment requests. The NRC staff 

6 does not ordinarily review other previously accepted actions, if they are not part of the 

7 application under review, unless staff identifies issues with other aspects of facility operation; 

8 however, NRC review of previously accepted actions may provide useful information concerning 

9 the operations and the site.

10

11 Accompanying this SRP are appendices to assist staff in their detailed review. SRP Appendix A 

12 is guidance for staff to use solely for reviewing historical aspects of site performance for license 

13 renewals and amendments. SRP Appendix B provides a correlation between 10 CFR Part 40, 

14 Appendix A requirements and the subsection(s) in this SRP where the review standards and 

15 acceptance criteria for the requirements are met. SRP Appendix C is guidance on the use of 

16 the radium benchmark dose approach, which is used to support decommissioning activities 

17 described in Chapter 7. SRP Appendix D is guidance for decontamination of facilities and 

18 equipment prior to release for unrestricted use in support of license terminations. SRP 

19 Appendix E contains an outline recommended by the NRC staff for preparing site-specific facility

20 reclamation and stabilization cost estimates for review. SRP Appendix F contains the NRC’s 

21 safety culture policy statement.

22

23 The following is a brief overview of the NRC license review process.

24

25 General Review Procedure

26

27 Figure 1.1 outlines the general safety review process for obtaining a new license, renewal of an 

28 existing license, or an amendment to an existing license. This SRP is intended to cover only 

29 those aspects of the safety review associated with the licensing of conventional uranium mills or 

30 heap leach facilities. The first step is submittal of an application by an applicant. After all 

31 documents have been properly submitted, typically a technical report and an environmental 

32 report, the NRC staff will then conduct acceptance reviews to evaluate whether sufficient 

33 information is contained in the application documents to conduct detailed reviews. For safety 

34 reviews, the focus is on the applicant’s technical report. If the application and supporting 

35 documents are not sufficient for a detailed safety review, then the staff will not docket the 

36 application and supporting documents. If the application and supporting documents are 

37 sufficient for a detailed safety review, then staff will docket the application and supporting 

38 documents. The next step is conducting a detailed examination of the docketed documents for 

39 acceptability or inadequacy of information. If appropriate, staff will develop requests for 

40 additional information (RAIs) for incomplete, inadequate, or unclear information in the 

41 docketed documents.

42

43 The staff typically issues RAIs when the information given in a license application is not 

44 sufficient for staff to make a licensing decision. The applicant will supplement the docketed 

45 application package by responding to the RAIs from the NRC. If staff still finds the information 

46 to be incomplete, inadequate, or unclear, then the staff discusses these open issues with the 

47 applicant to give the applicant another opportunity to provide the necessary information. The 

48 staff documents its determination of whether the proposed activities protect public health and
Executive Summary

xiv

Figure 1.1 General Safety Review Process

1

2 safety and comply with applicable regulations in a SER or TER, depending on the licensing 

3 action. If necessary, license conditions may be established after discussions with the applicant 

4 to protect public health and safety and ensure compliance with regulations. In the SER or TER, 

5 if staff finds that operations can be conducted in accordance with regulations and in a safe 

6 manner, then a license is issued, which may contain license conditions. If the staff finds that 

7 operations will be unsafe, then a license will not be issued. A source material application also

8 may be denied or rejected under specific instances during the review process. For example, the 

9 applicant’s failure to demonstrate compliance with 10 CFR 40.31(h) or refusal or failure to 

10 supply information staff requested to complete the review in accordance with 10 CFR 2.108 is 

11 also grounds for denial of the application.

12

13 The following are review objectives for conducting the safety application review.

14

15 Acceptance (Administrative) Review Objectives

16

17 The staff conducts an acceptance review of the technical report in the license application. The 

18 acceptance review serves two purposes: an administrative review to determine the 

19 completeness of the information submitted and a limited review to identify any potential 

20 regulatory compliance issues. This review involves a comparison of the submitted information 

21 to the information needs identified in this SRP. The application will be considered complete for 

22 docketing if the information provided is complete, reflects an adequate reconnaissance and 

23 physical examination of the regional and local site conditions, and provides appropriate 

24 analyses and design information. The acceptance review is very important because 
Executive Summary

xv

1 deficiencies in the license application materials may be identified early. This will ensure 

2 completeness of the application and result in fewer RAIs and a more efficient safety 

3 review process.

4

5 Detailed Technical Review Objectives 

6

7 Following completion of the acceptance review and the docketing of the application, the staff

8 conducts a detailed technical review of the application. As previously stated, results of this 

9 review and the basis for acceptance or denial of the requested licensing action are documented

10 in an SER or TER, depending on the licensing action. A detailed review should evaluate the 

11 technical information submitted by the applicant to confirm the ability of the proposed facility to 

12 meet applicable regulatory requirements.

13

14 Standard Review Plan Organization

15

16 This SRP is written to address a variety of potential site conditions and facility designs for the 

17 detailed safety review. Each section provides areas of review, review procedures, acceptance 

18 criteria, evaluation findings, and references subsections. The sections typically reflect 

19 significant health and safety concerns that would need to be addressed for the activity for which 

20 the SRP was developed. For any given application, the staff may select and emphasize 

21 particular aspects of each SRP section, as appropriate for the application. Therefore, the staff 

22 may not carry out all of the review steps listed in each SRP section in the review of 

23 every application.

24

25 Areas of Review Subsection

26

27 This subsection describes the scope of the review (i.e., what is being reviewed). It contains a 

28 brief description of the specific technical information and analyses in the application that staff 

29 should review.

30

31 Review Procedures Subsection

32

33 This subsection lists items and topics that the staff may review to assess compliance with 

34 regulations or accepted procedures. In this SRP, the review procedures are linked to 

35 specific regulations.

36

37 Acceptance Criteria Subsection

38

39 This subsection forms the basis for staff reviews and analyses in the SER or TER and provides 

40 specific guidance for review steps. It states the appropriate acceptance criteria to be reviewed 

41 and generally a step-by-step procedure that staff may use to determine whether the acceptance 

42 criteria have been met.

43

44 Evaluation Findings Subsection

45

46 The evaluation findings need to address the unique nature of the application or specific site 

47 conditions and proposed practices. If the information is adequate and complete and the staff 

48 finds that the application meets the applicable acceptance criteria, then typically a single 

49 paragraph is sufficient for the staff to conclude that the applicant has shown compliance with 

50 applicable regulations. In its analysis, the staff should include the justification as to why the

51 applicant has shown compliance with applicable regulations. If the information is inadequate or 
Executive Summary

xvi

1 incomplete, then the staff should explain why the applicant has not shown compliance with 

2 applicable regulations and impose a license condition, if necessary.

3

4 The Evaluation Findings Subsection is written so that guidance is given to staff for including four 

5 elements. The first element states what technical criteria were used to review the application 

6 and that the review was performed in accordance with a specified section in the SRP. The 

7 second element states what the applicant provided in the application and states why the 

8 provided information is complete and adequate or incomplete or inadequate. If the information 

9 is complete and adequate, then statements are given that explain why the information is 

10 complete and adequate. If the information is incomplete or inadequate, then statements are 

11 given that describe why the information is incomplete or inadequate. If needed, a third element 

12 may state that a license condition is being imposed to address the incomplete or inadequate 

13 information with respect to a specific technical criterion. In a following sentence, the license 

14 condition is stated. Note that more than one license condition may be associated with each 

15 technical criterion being reviewed. Finally, the fourth element states that the information 

16 provided, including any imposed license conditions, meets the applicable acceptance criteria of 

17 the applicable section of the SRP. The fourth element also states clearly the regulations to 

18 which the technical criteria apply.

19

20 References Subsection 

21

22 This subsection lists any applicable references that are cited in the preceding subsections. To 

23 avoid duplication of references, it is possible to list all references in one section of the SER or 

24 TER.

25

26 Standard Review Plan Updates

27

28 The staff will revise and update this SRP periodically as the need arises to clarify the content,

29 correct errors, or to incorporate review modifications approved by NRC management. 

30

31 NRC Safety Culture

32

33 Individuals and organizations performing regulated activities are expected to establish and 

34 maintain a positive safety culture commensurate with the safety and security significance of 

35 their activities and the nature and complexity of their organizations and functions. This applies 

36 to all licensees, certificate holders, permit holders, authorization holders, holders of quality 

37 assurance program approvals, vendors and suppliers of safety-related components, and 

38 applicants for a license, certificate, permit, authorization, or quality assurance program approval, 

39 subject to NRC authority.

40 “Nuclear safety culture” is defined in the safety culture policy statement as the core values and 

41 behaviors resulting from a collective commitment by leaders and individuals to emphasize 

42 safety over competing goals to ensure protection of people and the environment. (Appendix F 

43 of this SRP). Individuals and organizations performing regulated activities bear the primary 

44 responsibility for safely handling and securing these materials. Experience has shown that 

45 certain personal and organizational traits are present in a positive safety culture. A trait, in this 

46 case, is a pattern of thinking, feeling, and behaving that emphasizes safety, particularly in goal47 conflict situations (e.g., production versus safety, schedule versus safety, and cost of the effort 

48 versus safety). Refer to Table 1.1 for the traits of a positive safety culture from NRC’s safety 

49 culture policy statement.
Executive Summary

xvii

Table 1.1. Traits of a Positive Safety Culture

Leadership Safety Values

and Actions

Problem Identification and 

Resolution Personal Accountability

Leaders demonstrate a 

commitment to safety in their 

decisions and behaviors 

Issues potentially impacting 

safety are promptly 

identified, fully evaluated, 

and promptly addressed and 

corrected commensurate 

with their significance 

All individuals take personal 

responsibility for safety 

Work Processes Continuous Learning

Environment for Raising 

Concerns

The process of planning and 

controlling work activities is 

implemented so that safety 

is maintained 

Opportunities to learn about 

ways to ensure safety are 

sought out and implemented 

A safety conscious work 

environment is maintained 

where personnel feel free to 

raise safety concerns without 

fear of retaliation, 

intimidation, harassment or 

discrimination 

Effective Safety 

Communications

Respectful Work 

Environment Questioning Attitude

Communications maintain a 

focus on safety 

Trust and respect permeate 

the organization 

Individuals avoid 

complacency and continually 

challenge existing conditions 

and activities in order to 

identify discrepancies that 

might result in error or 

inappropriate action 

1

2 The NRC, as the regulatory agency with an independent oversight role, reviews the 

3 performance of individuals and organizations to determine compliance with requirements and 

4 commitments through its existing inspection and assessment processes. However, NRC’s 

5 safety culture policy statement and traits are not incorporated into the regulations. Many of the 

6 safety culture traits may be inherent to an organization’s existing radiation safety practices and 

7 programs. For instance, the requirement for daily inspections of tailings or waste retention 

8 systems may correspond with the “work processes” (the process of planning and controlling 

9 work activities is implemented so that safety is maintained) safety culture trait. Additionally, the 

10 requirement for establishment of a detection monitoring system to detect leakage of hazardous 

11 constituents from the tailings disposal area may correspond with the “problem identification and 

12 resolution” (issues potentially impacting safety are promptly identified, fully evaluated, and 

13 promptly addressed and corrected commensurate with their significance) safety culture trait. 
Executive Summary

xviii

1 More information on NRC activities relating to safety culture can be found at 

2 http://www.nrc.gov/about-nrc/regulatory/enforcement/safety-culture.html.

3 References

4

5 NRC. NUREG–1748, “Environmental Review Guidance for Licensing Actions Associated With 

6 NMSS Programs.” Washington, DC: NRC, Office of Nuclear Material Safety and Safeguards. 

7 August 2003.

8
1-1

1 1.0 PROPOSED ACTIVITIES

2

3 1.1 Areas of Review 

4

5 The purpose of this section of the standard review plan (SRP) is to provide a general overview 

6 of the proposed activities so that staff can gain a basic understanding of those proposed 

7 activities and the likely consequences of any public health and safety impacts. It is important for 

8 staff to obtain an overview of the proposed operations before initiating a detailed review of 

9 individual aspects of the source and 11e.(2) byproduct materials license application. For 

10 example, site location and layout, milling facilities, surface impoundments (including tailings 

11 impoundments, retention ponds, barren solution ponds, and heap leach pads), operations 

12 (including the maximum production rate for which a license is to be granted or amended), 

13 management, safety training, waste management, monitoring, and decommissioning plans, as 

14 well as other activities should be discussed in general terms. The overview needs to be 

15 consistent with other sections of the license application and needs to reflect how the license or 

16 amendment is to be written. Inconsistencies in the license application may result in a greater 

17 number of requests for additional information, significantly lengthening the license application 

18 review process. Specific details of the proposed activities can be discussed in other sections of 

19 the SRP where it is appropriate. Although some details may not be available for all activities at 

20 the time of the license application review, the reviewer should be provided enough information 

21 to obtain a basic understanding of the proposed activities and potential public health and 

22 safety impacts. 

23

24 1.2 Review Procedure

25

26 Ensure that the summary of proposed activities in the application provides a basic and sufficient 

27 understanding of the proposed activities and the likely magnitude of any public health and safety 

28 impacts. This information should meet, in part, the requirements of 10 CFR 40.31.

29

30 1.3 Acceptance Criterion

31

32 The summary descriptions of the proposed activities are acceptable if they are sufficiently 

33 detailed to provide a basic understanding of the activities for which a license or amendment is 

34 requested, and include the following: 

35

36 (a) Location of proposed facilities by county and state, including the facility name.

37

38 (b) Corporate entities involved, including ownership.

39

40 (c) Land ownership.

41

42 (d) Maximum instantaneous (gallons per minute) and permitted annual (lbs U3O8)

43 production rates of the mill (operations: tonnage of ore brought to the site and

44 yellowcake production). The maximum permitted rate for which a license is to be written 

45 or amended needs to be clearly listed and consistent throughout the license application. 

46

47 (e) Ore-body locations and estimated uranium content [Note: The U.S. Nuclear 

48 Regulatory Commission (NRC) regulates milling operations, not mining operations. The 

49 U.S. Department of Interior Office of Surface Mining, the U.S. Department of Labor Mine 

50 Safety and Health Administration, and the individual states regulate mining operations.
Proposed Activities

1-2

1 The information on ore body location and estimated uranium content is for 

2 understanding milling operations.]

3

4 (f) Milling process.

5

6 (g) Estimated schedules for construction, startup, and duration of operations.

7

8 (h) Plans for surface impoundments management.

9

10 (i) Plans for decommissioning and land reclamation.

11

12 (j) Plans for operational and postoperational monitoring.

13

14 (k) Financial assurance arrangements covering eventual facility decommissioning, site 

15 reclamation, and long-term monitoring.

16

17 (l) For license renewals, a summary of proposed changes, a record of amendments since 

18 the last license issuance, documentation of inspection results, and other relevant 

19 historical information.

20

21 1.4 Evaluation Findings

22

23 If the staff determines that no license conditions are required for the summary of proposed 

24 activities because the applicant or licensee provided adequate and complete information that 

25 fully addresses all relevant regulatory requirements, typically a single paragraph is sufficient for 

26 the evaluation findings section. Begin the section with the sentence: “NRC staff has completed 

27 its review of the summary of proposed activities at the conventional uranium mill or heap leach 

28 facility in accordance with Section 1.3 of the standard review plan.” Following this sentence, 

29 state what information the applicant provided in the application. As discussed in the introduction 

30 of this SRP, a bullet list or sentence format may be used to describe the information the 

31 applicant has provided. 

32

33 After the description of the information the applicant provided, the following or a similar

34 statement can be added: “Based on the review conducted by NRC staff, the information 

35 provided in the application meets the applicable acceptance criteria of Section 1.3 of the 

36 standard review plan. Therefore, NRC staff concludes that the applicant’s summary of 

37 proposed activities is acceptable and is in compliance 10 CFR 40.31, which describes the 

38 general requirements for the issuance of a specific license.” As a concluding statement, 

39 indicate the reason why the applicant’s information is considered adequate and complete, and 

40 why or how that information complies with the identified regulatory requirements. 

41

42 If license conditions are needed, then a more detailed discussion is typically required. Begin 

43 this section with the sentence: “NRC staff has completed its review of the summary of proposed 

44 activities at the conventional uranium mill or heap leach facility in accordance with Section 1.3 of 

45 the standard review plan.” Following this sentence, state what information the applicant 

46 provided in the application, including identification of the information that was omitted or 

47 inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

48 used to list what information the applicant has provided. Next, state why a license condition is 

49 needed, followed by the license condition or conditions. 
Proposed Activities

1-3

1 In a separate paragraph following the discussion of the required license condition(s), include the 

2 statement: “Based on the review conducted by NRC staff, the information provided in the 

3 application, supplemented by provisions of the license condition(s) discussed above, meets the 

4 applicable acceptance criteria of Section 1.3 of the standard review plan. Therefore, NRC staff 

5 concludes that the applicant’s summary of proposed activities is acceptable and is in 

6 compliance with 10 CFR 40.31, which describes the general requirements for the issuance of a 

7 specific license.” If not discussed in the preceding paragraph, include a statement or 

8 summation as to why or how the application and license condition(s) jointly comply with the 

9 identified regulatory requirements.

10

11 1.5 References

12

13 None.

2-1

1 2.0 SITE CHARACTERIZATION

2

3 2.1 Site Location and Layout

4

5 2.1.1 Areas of Review 

6

7 The staff should review regional and local geographic maps, topographic maps, and drawings 

8 that identify the conventional uranium mill or heap leach facility and its location relative to 

9 federal, state, county, and other political subdivisions. This should include maps provided to 

10 show the location and layout of the proposed facilities, principal structures (e.g., milling 

11 buildings, heap, ore stockpiles, surface impoundments, recovery plant buildings, diversion 

12 channels, drains, berms, and other major structures), supply wells, restricted area and site 

13 boundaries, fences, adjacent properties, site topography, property ownership, and land use. 

14

15 The regional location and site layout for the proposed operations should be reviewed using 

16 maps that show the relationship of the site to local water bodies (lakes, ponds, streams, 

17 wetlands, and springs); geomorphologic features (highlands, depression zones, areas of 

18 subsidence); transportation links (roads, rails, airports, waterways); political subdivisions 

19 (counties and townships); population centers (cities, towns); and nonapplicant property (farms, 

20 ranches, settlements). A contour map of the site showing a plan layout of construction and 

21 significant topographic variations of the site environs should be evaluated.

22

23 Staff should ensure that sufficient information about natural surface and subsurface systems is 

24 presented to reach the conclusion necessary for initial licensing.

25

26 2.1.2 Review Procedures

27

28 Use the following procedures when reviewing the characterization of the site layout 

29 and location:

30

31 (1) Establish the validity and completeness of the basic data to determine that the site 

32 location and layout proposed in the application are complete and accurate and that the 

33 site information is sufficient to evaluate the location of the proposed facilities relative to 

34 key features and activities. Verify that the applicant provided sufficient site-specific 

35 information to evaluate the suitability of the location of surface impoundments. 

36 This information should meet, in part, the requirements of 10 CFR 40.31(h) and

37 10 CFR Part 40, Appendix A, Criteria 1 and 4(b).

38

39 (2) Verify that maps showing the proposed conventional uranium mill or heap leach 

40 facility provided in the application are clear and readable and at an appropriate 

41 scale. This information should meet, in part, the requirements of 10 CFR 40.31(h) and

42 10 CFR Part 40, Appendix A, Criterion 1.

43

44 (3) Verify that the data sources supporting the description of site location and site layout of 

45 the proposed facility are clearly described. This information should meet, in part, the 

46 requirements of 10 CFR 40.31(h).

47

48 (4) Verify that the regional and site-specific geomorphic features, in particular those that 

49 may adversely affect site stability and integrity of surface impoundments, are adequately
Site Characterization

2-2

1 identified. This information should meet, in part, the requirements of 10 CFR Part 40,

2 Appendix A, Criteria 1, 3, 4(a), and 4(b).

3

4 2.1.3 Acceptance Criteria

5

6 The characterization of the proposed site location and layout is typically acceptable if it meets 

7 the following criteria:

8

9 (1) Data presented in the form of maps, drawings, tables, figures, and charts in support of 

10 site characterization of the proposed facility are complete and accurate. Such data 

11 include sufficient information on the following:

12

13 (a) Locations of planned principal structures, such as milling buildings, surface

14 impoundments (as described in Introduction), diversion channels, and recovery 

15 plant buildings. Data clearly show that sufficient land space is available for these 

16 principal structures at the proposed site.

17

18 (b) Restricted and site boundaries, ore stockpiles, berms, curbs, buffer zones, 

19 and fences.

20

21 (c) Current adjacent properties, including surface water bodies, forests, farms, 

22 ranches, settlements, property and mineral ownership, and federal, state, county, 

23 and local political subdivisions.

24

25 (d) Nearby population centers (e.g., towns, cities, and ranches) and transportation 

26 links such as railroads, highways, and waterways at present and for the 

27 anticipated life of the conventional uranium mill or heap leach facility.

28

29 (e) Elevation contours that show on a topographic map the boundaries of drainage 

30 basins and variations in the drainage gradient in the vicinity of the proposed 

31 conventional uranium mill or heap leach facility. The topographic map also 

32 includes surface drainage features upstream and downstream of the proposed 

33 surface impoundments. Topographic maps are in sufficient detail to assess

34 whether topographic features would provide good wind protection for surface

35 impoundments and minimize potential for extreme surface erosion, mass 

36 wasting, and stream encroachments. A proper siting for surface impoundments 

37 is crucial for meeting 1,000-year longevity without the use of active maintenance

38 in conformance with NUREG–1620, “Standard Review Plan for the Review of a 

39 Reclamation Plan for Mill Tailings Sites Under Title II of the Uranium Mill Tailings 

40 Radiation Control Act of 1978,” Revision 1 (NRC, 2003). The specific locations 

41 of natural streams and proposed diversion channels, relative to principal 

42 structures, are also provided. 

43

44 (f) Descriptions of the nature and extent of projected land use (e.g., agriculture, 

45 recreation, industry, livestock grazing, and infrastructure) and descriptions of the 

46 methodology and sources used to develop projections. Land use data are

47 collected within a 3.2-km [2-mi] distance from the site boundary. Information on 

48 residences within the 3.2-km [2-mi] distance is provided.

49

50 (g) Locations of uranium ore mines or mineral or resource recovery sites;

51 abandoned, in remediation, in operation, or proposed uranium and other mineral
Site Characterization

2-3

1 or resource recovery operations; nuclear fuel cycle facilities within an 80-km 

2 [50-mi]-geographic radius of the site.

3

4 (h) Locations of abandoned, properly or improperly plugged wells, borings, 

5 exploratory holes, and mine shafts. The applicant has properly assessed 

6 whether or not these previous features are properly plugged and provide 

7 information on methods of assessment. The staff should review information on 

8 the depth of these abandoned or plugged features at and near the proposed site.

9 If detailed information on locations of water supply and monitoring wells is not 

10 available at the time of the initial facility application, expected well locations are 

11 provided with an indication that the information is preliminary.

12

13 (2) Maps described in Section 2.1.1 of this standard review plan (SRP) are at an appropriate 

14 scale and are clear and readable. Maps include designation of scale, orientation 

15 (e.g., north arrow), and geographic coordinates. The proposed conventional uranium 

16 mill or heap leach facility is clearly labeled at a scale appropriate to the area being 

17 covered (regional and local) and with sufficient clarity and detail to allow identification 

18 and evaluation of the proposed facility. Any maps previously submitted (e.g., maps from 

19 the original application in the case of renewals) are legible, and actual or proposed 

20 changes are highlighted. In addition to maps, the applicant may provide tabular 

21 locations of facilities using standard, established geographic coordinate systems.

22

23 (3) Data sources are documented in reports such as U.S. Geological Survey open files or 

24 existing published maps. If the applicant generated data, the data documentation 

25 includes a description of the investigation and data reduction techniques.

26

27 (4) Regional and site-specific geomorphology and geomorphic processes are described in 

28 general. The description addresses the current geomorphological features and potential

29 geomorphological changes in the course of construction and operation phases at the 

30 site. This information is used, in part, to support the geomorphic and geotechnical 

31 stability of the site, which will be reviewed in detail in Section 2.6 of this SRP. 

32

33 2.1.4 Evaluation Findings

34

35 If the staff determines that no license conditions are required for site characterization because 

36 the applicant or licensee provided adequate and complete information that fully addresses all 

37 relevant regulatory requirements, typically a single paragraph is sufficient for the evaluation 

38 findings section. Begin the section with the sentence: “NRC staff has completed its review of 

39 the site characterization information concerned with site location and layout at the conventional 

40 uranium mill or heap leach facility in accordance with Section 2.1.3 of the standard review plan.” 

41 Following this sentence, state what information the applicant provided in the application. As 

42 discussed in the introduction of this SRP, a bullet list or sentence format may be used to list 

43 what information the applicant has provided. 

44

45 After the description of the information the applicant provided, the following or a similar

46 statement can be added: “Based on the review conducted by NRC staff, the information 

47 provided in the application meets the applicable acceptance criteria of Section 2.1.3 of the 

48 standard review plan. Therefore, NRC staff concludes that the applicant’s site characterization 

49 information is acceptable and is in compliance with 10 CFR 40.31(h), which requires 

50 completeness and accuracy in all materials provided by an applicant; 10 CFR Part 40, 

51 Appendix A, Criterion 1, the goal of which is isolation of the proposed facility; 10 CFR Part 40, 
Site Characterization

2-4

1 Appendix A, Criterion 3, which requires reasonable isolation of the tailings from natural 

2 erosional forces; and 10 CFR Part 40, Appendix A, Criteria 4, which requires that site design 

3 criteria need to be adhered to whether the tailings are located above or below grade.” As a 

4 concluding statement, indicate the reason why the applicant’s information is considered 

5 adequate and complete, and why or how that information complies with the identified 

6 regulatory requirements.

7

8 If license conditions are needed, then a more detailed discussion is typically required. Begin 

9 this section with the sentence: “NRC staff has completed its review of the site characterization 

10 information at the conventional uranium mill or heap leach facility in accordance with 

11 Section 2.1.3 of the standard review plan.” Following this sentence, state what information the 

12 applicant provided in the application, including identification of the information that was omitted 

13 or inadequate. As discussed in the introduction of this SRP, a bullet list or sentence format may 

14 be used to list what information the applicant has provided. Next, state why a license condition 

15 is needed, followed by the license condition or conditions.

16

17 In a separate paragraph following the discussion of the required license condition(s), include the 

18 statement: “Based on the review conducted by NRC staff, the information provided in the 

19 application, supplemented by provisions of the license condition(s) discussed above, meets the 

20 applicable acceptance criteria of Section 2.1.3 of the standard review plan. Therefore, NRC 

21 staff concludes that the applicant’s site characterization information is acceptable and is in 

22 compliance with 10 CFR 40.31(h), which requires completeness and accuracy in all materials 

23 provided by an applicant,10 CFR Part 40, Appendix A, Criterion 1, the goal of which is isolation 

24 of the proposed facility; 10 CFR Part 40, Appendix A, Criterion 3, which requires reasonable

25 isolation of the tailings from natural erosional forces; and 10 CFR Part 40, Appendix A, 

26 Criterion 4, which requires that site design criteria needs to be adhered to whether the tailings 

27 are located above or below grade.” If not discussed in the preceding paragraph(s), include a 

28 statement or summation as to why or how the application and license condition(s) jointly comply 

29 with the identified regulatory requirements.

30

31 2.1.5 Reference

32

33 NRC. NUREG–1620, “Standard Review Plan for the Review of a Reclamation Plan for Mill 

34 Tailings Sites Under Title II of the Uranium Mill Tailings Radiation Control Act of 1978.” Rev. 1. 

35 Washington, DC: U.S. Nuclear Regulatory Commission. June 2003.

36

37 2.2 Historical Investigations

38

39 2.2.1 Areas of Review

40

41 Abandoned or active man-made features penetrating through unsaturated zones may act as 

42 preferential contaminant pathways, through which contaminants may be conveyed from ground 

43 surface and unsaturated zones to the underlying water-bearing units. For example, abandoned 

44 wells, exploratory drillings, and boreholes resulting from historical site investigations may form 

45 pathways for surface impoundment leakage, if not plugged properly. Therefore, for new license 

46 applications, staff should review previous activities that may affect subsequent monitoring 

47 programs or provide potential for chemical migration. Staff should review the description and 

48 scope of historical site investigations undertaken by former site owners and third parties. This 

49 will aid in site characterization and help identify locations of abandoned boreholes, open pit 

50 mines, and mine shafts, including their current status. The third parties may include, but are not 
Site Characterization

2-5

1 limited to, State and Federal agencies (e.g., U.S. Geological Survey, U.S. Bureau of Land 

2 Reclamation, U.S. Bureau of Mines), universities, mining companies, prospectors, or oil and gas 

3 exploration companies.

4

5 2.2.2 Review Procedures

6

7 Use the following procedure when reviewing historical investigations:

8

9 (1) Examine whether the information on historical site characterizations is complete. This 

10 information should meet, in part, the requirements of 10 CFR 40.31(h).

11

12 (2) Verify that the applicant provided either official records or evidence that action was 

13 undertaken to properly plug and abandon wells and exploratory drill holes. This 

14 information should meet, in part, the requirements of 10 CFR 40.31(h).

15

16 (3) Verify that all maps containing data on historical investigations are at an appropriate 

17 scale and are readable. This information should meet, in part, the requirements of

18 10 CFR 40.31(h).

19

20 2.2.3 Acceptance Criteria

21

22 The historical investigations are typically acceptable if they meet the following criteria:

23

24 (1) A summary of historical investigations is provided. The summary clearly identifies the 

25 previous investigators, the scope of investigation, equipment used, investigation dates 

26 and durations, and investigation locations.

27

28 (2) Well plugging and abandonment records (including well depth, well materials, and their 

29 plugging status) obtained from state, federal, and local sources, as appropriate, are 

30 provided. Well plugging and abandonment records are sufficiently clear to allow 

31 evaluation of potential connections or preferential pathways through the ground surface 

32 where conventional uranium mill or heap leach activities take place, uppermost 

aquifers,

1 33 and underground sources of drinking water. For wells without plugging and 

34 abandonment records, the applicant provides evidence that action is underway to 

35 properly plug and abandon wells. 

36

37 (3) Maps containing data on historical investigations provided are at sufficient scale and 

38 resolution to clearly show the locations of historical site explorations, such as borings, 

39 exploratory drillings, trenches, and seismic lines.

40

41 2.2.4 Evaluation Findings

42

43 If the staff determines that no license conditions are required for historical investigations 

44 because the applicant or licensee provided adequate and complete information that fully 

45 addresses all relevant regulatory requirements, typically a single paragraph is sufficient for the 

46 evaluation findings section. Begin the section with the sentence: “NRC staff has completed its 

47 review of historical investigations at the conventional uranium mill or heap leach facility in 

 1

Uppermost aquifer means the geologic formation nearest the natural ground surface that is an aquifer, as well 

as lower aquifers that are hydraulically interconnected with this aquifer within the facility’s property boundary 

(10 CFR Part 40, Appendix A, Definition).
Site Characterization

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1 accordance with Section 2.2.3 of the standard review plan.” Following this sentence, state 

2 what information the applicant provided in the application. As discussed in the introduction 

3 of this SRP, a bullet list or sentence format may be used to list what information the applicant 

4 has provided. 

5

6 After the description of the information the applicant provided, the following or a similar

7 statement can be added: “Based on the review conducted by NRC staff, the information 

8 provided in the application meets the applicable acceptance criteria of Section 2.2.3 of the 

9 standard review plan. Therefore, NRC staff concludes that the applicant’s historical 

10 investigations are acceptable and are in compliance with 10 CFR 40.31(h), which requires 

11 completeness and accuracy in all materials provided by an applicant.” As a concluding 

12 statement, indicate the reason why the applicant’s information is considered adequate and 

13 complete, and why or how that information complies with the identified regulatory requirements.

14

15 If license conditions are needed, then a more detailed discussion is typically required. Begin 

16 this section with the sentence: “NRC staff has completed its review of historical investigations 

17 at the conventional uranium mill or heap leach facility in accordance with Section 2.2.3 of the 

18 standard review plan.” Following this sentence, state what information the applicant provided in 

19 the application, including identification of the information that was omitted or inadequate. As 

20 discussed in the introduction of this SRP, a bullet list or sentence format may be used to list 

21 what information the applicant has provided. Next, state why a license condition is needed, 

22 followed by the license condition or conditions. 

23

24 In a separate paragraph following the discussion of the required license condition(s), include the 

25 statement: “Based on the review conducted by NRC staff, the information provided in the 

26 application, supplemented by provisions of the license condition(s) discussed above, meets the 

27 applicable acceptance criteria of Section 2.2.3 of the standard review plan. Therefore, NRC 

28 staff concludes that the applicant’s historical investigations are acceptable and are in 

29 compliance with 10 CFR 40.31(h), which requires completeness and accuracy in all materials 

30 provided by an applicant.” If not discussed in the preceding paragraph(s), include a statement

31 or summation as to why or how the application and license condition(s) jointly comply with the 

32 identified regulatory requirements.

33

34 2.2.5 References

35

36 None.

37

38 2.3 Meteorology

39

40 2.3.1 Areas of Review 

41

42 Staff should review descriptions of the atmospheric diffusion characteristics of the site and its 

43 surrounding area based on onsite meteorological data. Staff also should review a discussion of 

44 the general climatology including precipitation, evaporation, existing air quality, the relationship 

45 of the regional meteorological data to the onsite data, the meteorological impact of the onsite

46 terrain and large lakes and other bodies of water, and the occurrence of severe and extreme 

47 weather in the area and its effects. This review also should include information on wind speed 

48 and direction, average temperature, and relative humidity. The meteorology program—which is 

49 part of the site monitoring programs required by 10 CFR Part 40, Appendix A, Criterion 7—

50 needs to be sufficiently complete to allow for estimating maximum potential annual radiation 
Site Characterization

2-7

1 doses to workers and members of the public resulting from the routine releases of airborne 

2 radioactive materials in gaseous and particulate effluents to demonstrate compliance with 

3 10 CFR 20.1101, 10 CFR 20.1302, 40 CFR 190.10, and 40 CFR Part 192.

4

5 2.3.2 Review Procedures

6

7 Use the following procedures when reviewing the site meteorology:

8

9 (1) Verify whether information on onsite meteorological conditions is sufficient to support 

10 environmental monitoring locations, estimates of airborne radionuclide transport from the 

11 proposed conventional uranium mill or heap leach facility to the unrestricted areas, and 

12 the performance of dose assessments to determine airborne pathway inputs to risk 

13 assessment models in conformance with Regulatory Guide 3.63, “Onsite Meteorological 

14 Measurement Program for Uranium Recovery Facilities—Data Acquisition and 

15 Reporting” (NRC, 1988). This information should meet, in part, the requirements of

16 10 CFR 20.1302 and 10 CFR Part 40, Appendix A, Criterion 7.

17

18 (2) Determine whether the applicant provided onsite meteorological data that are

19 representative of long-term meteorological data from a National Weather Service station. 

20 This information should meet, in part, the requirements of 10 CFR 20.1501 and 

21 10 CFR 40.31(h). 

22

23 (3) Review the description of existing radiological and nonradiological air quality. This 

24 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

25 Criterion 8; 40 CFR 50.6(a); and 40 CFR 50.7(a).

26

27 (4) Verify that the sources of meteorological and air quality data are documented in open file 

28 reports or other published documents and the references to those documents are 

29 provided. This information should meet, in part, the requirements of 10 CFR 40.31(h).

30

31 2.3.3 Acceptance Criteria

32

33 The minimum amount of meteorological data needed for a siting evaluation is considered to be 

34 that amount of data gathered on a continuous basis for a consecutive 12-month period that is 

35 representative of long-term weather patterns in accordance with Regulatory Guide 3.63 

36 (NRC, 1988). Consistent with the recommendation in Regulatory 3.63 (NRC, 1988), continuous 

37 sampling should continue until the applicant demonstrates that the data collected is 

38 representative of long-term conditions. The characterization of the site meteorology is 

39 acceptable if it meets the following criteria:

40

41 (1) Onsite meteorological conditions are described, based on appropriate data from National 

42 Weather Service, U.S. military, or other stations recognized as standard installations. 

43 The onsite meteorological data includes the following:

44

45 (a) Locations and heights of instrumentation, description of instrumentation, and 

46 joint-frequency distribution data by wind direction, wind speed, atmospheric 

47 stability, annual wind rose diagrams, and period of record in accordance with 

48 Regulatory Guide 3.63 (NRC, 1988), and ANSI/ANS-3.11-2005 (American 

49 Nuclear Society, 2005). Quarterly and annual wind direction, wind speed, and 

50 atmospheric stability data are compiled in terms of joint frequency and joint 
Site Characterization

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1 relative frequency, with an annual joint data recovery of 75 percent from heights 

2 representative of airborne gaseous releases (e.g., radon). The applicant may 

3 chose to use insulation-cloud cover and wind speed method, temperature lapse 

4 rate method, wind fluctuation method, Richardson method, or some other method 

5 to obtain information on atmospheric stability. The atmospheric stability 

6 classification scheme needs adjustment based on local influences such as 

7 surface roughness of terrain [ANSI/ANS-3.11-2005 (American Nuclear Society, 

8 2005)]. For individual meteorological parameters, an annual data recovery of

9 at least 90 percent in accordance with Regulatory Guide 3.63 (NRC, 1988)

10 is provided.

11

12 (b) Miscellaneous data, including average mixing layer heights (which defines the 

13 upper boundary of the volume through which contaminants are capable of being 

14 mixed), a description of regional climatology, daily-averaged and maximum 

15 ambient temperatures, monthly and annual time series of daily-totaled

16 precipitation and evaporation, and description of extreme weather conditions. 

17 Supplemental meteorological measurements could be necessary to address 

18 site-specific concerns, such as atmospheric motions in complex terrain, building 

19 wake-effects, which can potentially affect dispersion of effluents and airflow 

20 trajectories. Such supplementary meteorological measurements may include, 

21 but are not limited to, atmospheric moisture, solar and net radiation, barometric 

22 pressure, soil temperature in accordance with ANSI/ANS-3.11-2005 (American 

23 Nuclear Society, 2005).

24

25 (c) Maps or tables that describe meteorological conditions at the site and in the 

26 vicinity of the facility. In-situ measurements may also be augmented by 

27 remote-sensing technologies and supplemental monitoring locations especially 

28 for sites located in complex terrain environment (ANSI/ANS-3.11-2005).

29

30 (2) Meteorological data gathered on-site over a minimum 12-month consecutive period for a 

31 siting evaluation is representative of long-term (e.g., 30 years) meteorological conditions. 

32 To assess whether the period during which onsite meteorological data gathered are

33 representative of expected long-term conditions, the concurrent period of meteorological 

34 data from a National Weather Service station are compared with the long-term 

35 meteorological data from the same station. The National Weather Service station 

36 selected for this comparison is in a similar geographical and topographical location and 

37 is reasonably close to the site (preferably within 50 mi [80 km]), if possible. The 

38 assessment is consistent with the guidance provided in Regulatory Guide 3.63 

39 (NRC, 1988).

40

41 (3) Nonradiological air quality data (in reference to daily averaged PM10, daily averaged 

42 PM2.5, and annually averaged PM2.5, in which PMx stands for particulate matter of size 

43 less than and equal to x μm) collected over at least 1 full year prior to site construction 

44 are presented. If there has been significant changes or nearby construction, the air 

45 quality data should be collected in close temporal proximity to site construction. This 

46 type of data is preferred. However, if the area around a site remained unchanged 

47 between data collection and construction, it is possible to rely on the older data, if 

48 available. The U.S. Environmental Protection Agency (EPA) is concerned about PM7.5

49 and PM10, because once they are inhaled, they can affect heart and lungs and cause 

50 serious health effects. Radiological air quality parameters include, but are not limited to, 

51 radon levels.
Site Characterization

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1 (4) The sources of all meteorological and air quality data are documented in open file

2 reports or other published documents. If the applicant generated data, the data 

3 documentation includes a description of the investigations and data 

4 reduction techniques.

5

6 2.3.4 Evaluation Findings

7

8 If the staff determines that no license conditions are required for meteorology because the 

9 applicant or licensee provided adequate and complete information that fully addresses all 

10 relevant regulatory requirements, typically a single paragraph is sufficient for the evaluation 

11 findings section. Begin the section with the sentence: “NRC staff has completed its review of 

12 meteorology at the conventional uranium mill or heap leach facility in accordance with 

13 Section 2.3.3 of the standard review plan.” Following this sentence, state what information the 

14 applicant provided in the application. As discussed in the introduction of this SRP, a bullet list or 

15 sentence format may be used to list what information the applicant has provided. 

16

17 After the description of the information the applicant provided, the following or a similar

18 statement can be added: “Based on the review conducted by NRC staff, the information 

19 provided in the application meets the applicable acceptance criteria of Section 2.3.3 of the 

20 standard review plan. Therefore, NRC staff concludes that the applicant’s meteorological 

21 characterization is acceptable and is in compliance with 10 CFR 20.1101, which requires 

22 licensees to have a radiation protection program; 10 CFR 20.1302, which requires compliance 

23 with dose limits for individual members of the public; 10 CFR 20.1501, which requires surveys to 

24 establish the magnitude and extent of radiation levels, concentrations or quantities of 

25 radioactive material, and the potential radiological hazards; 10 CFR 40.31(h), which requires 

26 completeness and accuracy of information; 10 CFR Part 40, Appendix A, Criterion 7, which 

27 requires preoperational and operational monitoring programs; 10 CFR Part 40, Appendix A, 

28 Criterion 8, which requires that milling operations must be conducted such that airborne effluent 

29 releases are reduced to as low as is reasonably achievable (ALARA) levels; 40 CFR 50.6(a) 

30 and 40 CFR 50.7(a), which set the limits for national primary and secondary ambient air quality 

31 standards for PM10 and PM2.5, respectively; 40 CFR 190.10, which establishes environmental 

32 standards for normal operations; and 40 CFR Part 192, which establishes health and 

33 environmental protection standards for uranium and thorium mills.” As a concluding statement, 

34 indicate the reason why the applicant’s information is considered adequate and complete, and 

35 why or how that information complies with the identified regulatory requirements.

36

37 If license conditions are needed, then a more detailed discussion is typically required. Begin 

38 this section with the sentence: “NRC staff has completed its review of meteorology at the 

39 conventional uranium mill or heap leach facility in accordance with Section 2.3.3 of the standard 

40 review plan.” Following this sentence, state what information the applicant provided in the 

41 application, including identification of the information that was omitted or inadequate. As 

42 discussed in the introduction of this SRP, a bullet list or sentence format may be used to list 

43 what information the applicant has provided. Next, state why a license condition is needed, 

44 followed by the license condition or conditions. 

45

46 In a separate paragraph following the discussion of the required license condition(s), include the 

47 statement: “Based on the review conducted by NRC staff, the information provided in the 

48 application, supplemented by provisions of the license condition(s) discussed above, meets the 

49 applicable acceptance criteria of Section 2.3.3 of the standard review plan. Therefore, NRC 

50 staff concludes that the applicant’s meteorological characterization is acceptable and is in 
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1 compliance with 10 CFR 20.1101, which requires licensees to have a radiation protection 

2 program; 10 CFR 20.1302, which requires compliance with dose limits for individual members 

3 of the public; 10 CFR 20.1501, which requires surveys to establish the magnitude and extent 

4 of radiation levels, concentrations or quantities of radioactive material, and the potential 

5 radiological hazards; 10 CFR 40.31(h), which requires completeness and accuracy of 

6 information; 10 CFR Part 40, Appendix A, Criterion 7, which requires preoperational and 

7 operational monitoring programs; 10 CFR Part 40, Appendix A, Criterion 8, which requires that 

8 milling operations must be conducted such that airborne effluent releases are reduced to 

9 ALARA levels; 40 CFR 50.6(a) and 40 CFR 50.7(a), which set the limits for national primary and 

10 secondary ambient air quality standards for PM10 and PM2.5, respectively; 40 CFR 190.10, which 

11 establishes environmental standards for normal operations; and 40 CFR Part 192, which 

12 establishes health and environmental protection standards for uranium and thorium mills.” If 

13 not discussed in the preceding paragraph(s), include a statement or summation as to why 

14 or how the application and license condition(s) jointly comply with the identified 

15 regulatory requirements.

16

17 2.3.5 References

18

19 American Nuclear Society. ANSI/ANS-3-11, “American National Standard for Determining 

20 Meteorological Information at Nuclear Facilities.” La Grange Park, Il: American Nuclear 

21 Society. 2005.

22

23 NRC. Regulatory Guide 3.63, “Onsite Meteorological Measurement Program for Uranium 

24 Recovery Facilities—Data Acquisition and Reporting.” Washington, DC: U.S. Nuclear 

25 Regulatory Commission, Office of Nuclear Regulatory Research. 1988.

26

27 2.4 Geology and Seismology 

28

29 2.4.1 Areas of Review 

30

31 The reviewer should examine information on the geologic aspects of the site acquired through 

32 standard geologic analyses, including a survey of pertinent literature and field investigations. 

33 This information should include local (site-scale) and regional stratigraphy, horizontal and 

34 vertical extents of major geologic units at the site and regional scale, petrologic characteristics 

35 of major geologic units (e.g., thickness, composition), tectonic features (faults, folds, fractures, 

36 and joints), volcanic features (e.g., cones, plugs, and dikes), and regional seismicity and seismic 

37 history. Some of the applicant’s supporting information for this review area might be included in 

38 the documents submitted to satisfy the subsurface hydrology review area (see Section 2.7.1 of 

39 this SRP).

40

41 The staff should review the information presented on mining of economically important minerals 

42 (e.g., uranium or coal) and on energy-related deposits (e.g., coal-bed methane or oil 

43 production), including:

44

45 (1) Soil and geotechnical stability at, and near, the proposed facility;

46

47 (2) Changes in topographical features and drainage patterns that may affect surface water 

48 flooding and erosion and wind protection for surface impoundments; and

49
Site Characterization

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1 (3) Excessive dewatering of groundwater in the uppermost aquifer and/or affecting 

2 groundwater flow directions and rates in the uppermost aquifer, if the uppermost aquifer 

3 is a source for consumptive water use at other facilities.

4

5 Where applicable, the staff should perform independent analyses to verify the geologic data 

6 provided. The staff should also examine descriptions of any effects that planned operations at 

7 the site might have on the future availability of other mineral resources. 

8

9 2.4.2 Review Procedures

10

11 The staff should use the following procedure in performing the review of the site geology 

12 and seismology:

13

14 (1) Determine whether a thorough evaluation of the geologic setting, including near surface 

15 geology, for the proposed conventional uranium mill or heap leach site is presented 

16 along with the basic geological data supporting the applicant’s conceptual model of the 

17 geology. Determine whether stratigraphic units are described in sufficient detail to 

18 provide input to a geotechnical stability analysis review area as described in Section 2.6

19 of this SRP. This information should meet, in part, the requirements of 10 CFR 40.31(h).

20

21 (2) Determine whether the application contains accurate geologic, structural, and 

22 stratigraphic maps, isopach maps of the uppermost aquifer (as described in 

23 Section 2.2.3 of this SRP) and confining layer below the uppermost aquifer; geologic 

24 cross sections at places critical to a thorough understanding of the selected site;

25 descriptions of representative supporting core samples; geophysical and lithologic logs 

26 and surveys, trenches, and remote-sensing measurements; and other data required for 

27 a thorough understanding of the pertinent geology. This information should meet, in 

28 part, the requirements of 10 CFR 40.31(h), 10 CFR Part 40, Appendix A, Criteria 5B(3)

29 and 7. 

30

31 (3) Determine whether the regional stratigraphic, structural, and geologic information 

32 is discussed in sufficient detail to give clear perspective and orientation to the 

33 site-specific material presented. This information should meet, in part, the requirements 

34 of 10 CFR 40.31(h).

35

36 (4) Determine whether an inventory of regional and local economically significant mineral 

37 and energy-related deposits is provided. This information should meet, in part, the 

38 requirements of 10 CFR 40.31(h).

39

40 (5) Evaluate the discussion of the seismicity and the seismic history of the region. 

41 This information should meet, in part, the requirements of 10 CFR 40.31(h) and 

42 10 CFR Part 40, Appendix A, Criterion 4(e). 

43

44 (6) Verify that the sources of all geological and seismological data are documented in 

45 U.S. Geological Survey open files or other published documents. This information 

46 should meet, in part, the requirements of 10 CFR 40.31(h).

47

48 (7) Determine whether any volcanic features, such as solidified lava channels, cones, and 

49 dikes, if located in the proposed site, are discussed in sufficient detail. This information 

50 should meet, in part, the requirements of 10 CFR 40.31(h).

51
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1 The staff may also perform an independent analysis of the data provided to assess whether 

2 reasonable and conservative alternative interpretations are indicated. 

3

4 2.4.3 Acceptance Criteria

5

6 The characterization of the site geology and seismology is acceptable if it meets the 

7 following criteria: 

8

9 (1) A detailed description is presented of the geologic setting at the local and regional 

10 scales by including the description of the major rock types (stratigraphic units) and their

11 thickness, composition, orientation, distribution both at the surface and at the depths of 

12 interest, and continuity. Geological data and the sources to support the description of 

13 the geological setting at the proposed site are presented. Geological data may be 

14 included in the original work the applicant submitted or obtained from previous work in 

15 the region that third parties performed as discussed in Section 2.2 of this SRP. 

16 Geological data may be acquired through cuttings and core logging and through wireline 

17 geophysical logs, such as electrical resistivity, neutron density, and gamma logs. 

18 Surface geophysical methods may provide useful data. Geological descriptions of the 

19 proposed site may be presented as stratigraphic columns, geologic maps, cross 

20 sections, fence diagrams showing stratigraphic correlations among sampling locations, 

21 aerial photography, and remote sensing images. 

22

23 (2) The following information is presented:

24

25 (i) Geologic, structural, stratigraphic, and isopach maps of the uppermost aquifer,

26 the confining layer below the uppermost aquifer. Isopach maps for the confining 

27 layer below the uppermost aquifer may not be required, if sufficient local or 

28 regional data from literature or nearby mining or oil fields exist to confirm the

29 continuity and spatial uniformity (in thickness and porosity) of the confining layer. 

30 If the confining layer is discontinuous and it is underlain by a major aquifer, which 

31 is being used or could be used as a potential water source, then geologic, 

32 structural, stratigraphic, and isopach maps of the underlying major aquifer below 

33 the confining layer are presented. 

34

35 (ii) Geologic cross sections, with groundwater levels indicated (see Section 2.7 of 

36 this SRP), below the proposed surface impoundments and mill buildings and at 

37 other critical places at the proposed facility essential for a thorough 

38 understanding of the proposed site and description of representative 

39 core samples

40

41 (iii) Geophysical and lithological logs, remote-sensing measurements, and other data 

42 required for a thorough understanding of the pertinent geology.

43

44 All maps and cross sections are at sufficient scale and resolution to clearly show the 

45 intended geologic information and also include the location of major facility structures. 

46 Maps show sampling locations (e.g., geophysical logs, borehole locations) and geologic 

47 cross sections. Maps have designation of scale, orientation (e.g., north arrow), and 

48 geographic coordinates. Cross sections show groundwater elevations in the uppermost 

49 aquifer and also in the underlying major aquifer, if there is evidence that the underlying 

50 aquifer may not be hydraulically isolated.

51
Site Characterization

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1 (3) The discussion of regional geology and stratigraphy is adequately referenced and 

2 illustrated by regional surface and subsurface geologic maps, stratigraphic columns, and 

3 cross sections. A generalized stratigraphic column including the thicknesses and type of 

4 rock units and representation of lithologies is presented. In the local stratigraphic 

5 section, the uppermost aquifer, its underlying confinement, and other important 

6 underlying units, such as drinking water aquifers, are clearly shown with their depths 

7 from the surface.

8

9 The local and regional geologic structure, including folds, fractures, and faults, is

10 described with the aid of, for example, aerial photography, remote sensing images and 

11 field studies. Folds and faults are shown on the geologic maps used to describe the 

12 stratigraphy. Structural maps of faults are provided and fault offsets are shown on 

13 cross-section maps. Lateral facies changes of stratigraphic units and major structural 

14 features are shown in cross sections. Major and minor faults traversing the proposed 

15 site are evaluated for the likely consequences (e.g., their potential barrier effects or 

16 preferential pathways) of any future effects of active faulting on the stability of 

17 surface impoundments.

18

19 (4) An inventory of economically significant mineral and energy-related deposits is provided. 

20 Locations (via, for example, aerial photography, remote sensing images, or site visits) 

21 are provided for known wells, surface and underground mine workings, disturbed lands 

22 (e.g., construction zones, open pits, sites chosen for land application of treated produced 

23 water), and surface impoundments that may have an effect on the proposed operations. 

24 These items are located on a map of sufficient scale and clarity. 

25

26 (5) The seismicity and the seismic history of the region are discussed. Historical seismicity 

27 data are summarized on a regional earthquake epicenter map within 200 km [124 mi] of 

28 the site, including the date of occurrence, magnitude, and location of known seismic 

29 events [NUREG–1620 (NRC, 2003)]. Seismic events associated with the tectonic 

30 features are described in the geologic structures. 

31

32 The applicant provides deterministic and/or probabilistic seismic hazard analyses. For a 

33 deterministic analysis, the potential ground motion at the site from capable faults that 

34 might affect the integrity of surface impoundments, and hence, the licensed area, is

assessed.

2 35 A probabilistic seismic hazard analysis yields a curve of exceedance 

probability versus peak horizontal acceleration. The 10−4 36 value represents a 1 in 

37 10 chance of the site exceeding the peak horizontal acceleration in a 1,000-year period, 

38 which is appropriate for a 1,000-year design life. The applicant demonstrated that 

39 surface impoundments have been designed to withstand the credible earthquake (the 

40 largest earthquake that can reasonably be expected) the fault may generate. 

41 Additionally, the proposed designs for surface impoundments are shown to be capable 

42 of withstanding the liquefaction potential associated with the expected maximum ground 

43 acceleration from earthquakes (see Section 3.3 of this SRP).

44

45 (6) The sources of geological and seismological data are documented in 

46 U.S. Geological Survey open files or other published documents. If the applicant 

47 generated data, the documentation includes a description of the investigations and data 

48 reduction techniques.

 2

The term capable fault, as used in 10 CFR Part 40, Appendix A, Criterion 4(e), has the same meaning as defined in 

10 CFR Part 100, Appendix A, Section III(g).
Site Characterization

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1 (7) Volcanic features may act as flow conduits or barriers to groundwater flow, if they exist. 

2 Therefore, a discussion of volcanic features (such as dike, cone, and solidified lava 

3 channels), if they exist at the proposed site or nearby, is adequately referenced and 

4 interrelations among these features and with other geological (stratigraphic units) and 

5 structural features (joints, fractures, faults, folds), including geologic age relationships, 

6 are supported by maps, logs, and cross sections.

7

8 2.4.4 Evaluation Findings

9

10 If the staff determines that no license conditions are required for geology and seismology 

11 because the applicant or licensee provided adequate and complete information that fully 

12 addresses all relevant regulatory requirements, typically a single paragraph is sufficient for the 

13 evaluation findings section. Begin the section with the sentence: “NRC staff has completed its 

14 review of geology and seismology at the conventional uranium mill or heap leach facility in 

15 accordance with Section 2.4.3 of the standard review plan.” Following this sentence, state what 

16 information the applicant provided in the application. As discussed in the introduction of this 

17 SRP, a bullet list or sentence format may be used to list what information the applicant 

18 has provided. 

19

20 After the description of the information the applicant provided, the following or a similar

21 statement can be added: “Based on the review conducted by NRC staff, the information 

22 provided in the application meets the applicable acceptance criteria of Section 2.4.3 of the 

23 standard review plan. Therefore, NRC staff concludes that the applicant’s geology and 

24 seismology is acceptable and is in compliance with 10 CFR 40.31(h), which requires 

25 completeness and accuracy in all materials provided by an applicant; 10 CFR Part 40, 

26 Appendix A, Criterion 4(e), which requires locations away from faults capable of causing 

27 surface impoundment failure; 10 CFR Part 40, Appendix A, Criterion 5B(3), which establishes 

28 criteria for excluding a detected constituent; and 10 CFR Part 40, Appendix A, Criterion 7, which 

29 requires preoperational and operational monitoring programs.” As a concluding statement, 

30 indicate the reason why the applicant’s information is considered adequate and complete, and 

31 why or how that information complies with the identified regulatory requirements.

32

33 If license conditions are needed, then a more detailed discussion is typically required. Begin 

34 this section with the sentence: “NRC staff has completed its review of geology and seismology 

35 at the conventional uranium mill or heap leach facility in accordance with Section 2.4.3 of the 

36 standard review plan.” Following this sentence, state what information the applicant provided in 

37 the application, including identification of the information that was omitted or inadequate. As 

38 discussed in the introduction of this SRP, a bullet list or sentence format may be used to list 

39 what information the applicant has provided. Next, state why a license condition is needed, 

40 followed by the license condition or conditions. 

41

42 In a separate paragraph following the discussion of the required license condition(s), include the 

43 statement: “Based on the review conducted by NRC staff, the information provided in the 

44 application, supplemented by provisions of the license condition(s) discussed above, meets the 

45 applicable acceptance criteria of Section 2.4.3 of the standard review plan. Therefore, NRC 

46 staff concludes that the applicant’s geology and seismology is acceptable and is in 

47 compliance with 10 CFR 40.31(h), which requires completeness and accuracy in all 

48 materials provided by an applicant; 10 CFR Part 40, Appendix A, Criterion 4(e), which 

49 requires locations away from faults capable of causing surface impoundment failure;

50 10 CFR Part 40, Appendix A, Criterion 5B(3), which establishes criteria for excluding a 
Site Characterization

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1 detected constituent; and 10 CFR Part 40, Appendix A, Criterion 7, which requires 

2 preoperational and operational monitoring programs.” If not discussed in the preceding 

3 paragraph(s), include a statement or summation as to why or how the application and license 

4 condition(s) jointly comply with the identified regulatory requirements.

5

6 2.4.5 Reference

7

8 NRC. NUREG–1620, “Standard Review Plan for the Review of a Reclamation Plan for Mill 

9 Tailings Sites Under Title II of the Uranium Mill Tailings Radiation Control Act of 1978.” Rev. 1. 

10 Washington, DC: U.S. Nuclear Regulatory Commission. June 2003.

11

12 2.5 Soil

13

14 2.5.1 Areas of Review 

15

16 Characterization of the soil must be sufficient so that the staff can assess whether public health 

17 and safety may be affected by conventional uranium mill or heap leach facility operations

18 (e.g., surface impoundments design). Because soil properties affect several practices at 

19 conventional uranium mill and heap leach facilities, soil-related properties may be discussed in 

20 more detail in other sections; however, basic information needs to be presented in this section, 

21 including reporting the range in soil properties found at the facility site. Important soil 

22 characteristics are soil texture (percent sand, silt, and clay), coarse fragments (percentage of

23 gravels, cobbles, and boulders), organic matter content, clay mineralogy, soil depth, porosity, 

24 bulk density (oven-dry mass density of soil), permeability or saturated hydraulic conductivity, soil 

25 strength, and characteristics important for soil chemistry. Soil maps of the site should also be 

26 reported. The baseline (preoperational) radioactive content of the soil is reported in Section 2.8

27 of this SRP.

28

29 2.5.2 Review Procedures 

30

31 The staff should use the following procedure in performing the review of the site 

32 soil characterization:

33

34 (1) Determine whether a soil map is provided for the facility and whether there is a 

35 discussion relating soil types to landforms (e.g., valley bottoms, side slopes, terraces, 

36 ridge/hill tops) of the site. This information should meet, in part, the requirements of 

37 10 CFR 40.31(h); 10 CFR Part 40, Appendix A, Criteria 1 and 5G(2).

38

39 (2) Verify that soil properties are discussed and representative values and ranges are given 

40 for the various soil types (and layers) shown in the soil map. This information should 

41 meet, in part, the requirements of 10 CFR 40.31(h); 10 CFR Part 40, Appendix A, 

42 Criteria 1 and 5G(2).

43

44 The staff also should evaluate the methods used to characterize the soil properties to ensure 

45 that they are consistent with generally accepted standards, such as those of the ASTM 

46 International, the U.S. Department of Agriculture, or other industry standards (see Dane and 

47 Topp, 2002). 

48

49

50
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1 2.5.3 Acceptance Criteria

2

3 The characterization of the soil is acceptable if it meets the following criteria: 

4

5 (1) The application includes a map outlining boundaries among soil types or soil complexes 

6 (a mapping unit containing two or more soil types). The map is at a sufficient scale and 

7 resolution to show clearly the soil mapping units. A discussion accompanies the map 

8 describing how the soil types are associated with particular landforms or other pertinent 

9 information at the site. The use of a soil survey the Natural Resources Conservation 

10 Service of the U.S. Department of Agriculture conducted, if available, is adequate.

11

12 (2) Representative values (with ranges) of the following soil properties are given and are 

13 appropriate for conventional uranium mill or heap leach operations. At a minimum, 

14 values are reported for the surface (upper 5 cm [2 in]) and subsurface layers (at a depth 

15 of 1 m [3.3 ft] or shallower if soil depth is less than 1 m [3.3 ft]). Changes in soil 

16 properties, including depth, are noted. The methods used to determine the values are 

17 also given. Values the Natural Resources Conservation Service reported are 

18 acceptable. Soil descriptions should be based on U.S. Department of Agriculture soil 

19 taxonomy or soil science classification descriptions. The following soil properties 

20 are provided:

21

22 (a) Soil texture (percentage of sand, silt, and clay of the less than 2-mm [0.079-in] 

23 diameter size class)—if the particle size distribution is determined by sieve 

24 analyses, then the percentage passing through the 200-mesh sieve;

25

26 (b) Coarse fragments (percentage of gravels, cobbles, and boulders in the soil);

27

28 (c) Dominant mineralogy of the clay-sized particles (e.g., smectite or other swelling 

29 clays; kaolinite, allophane, or other nonswelling clays)—some indication of 

30 whether the clay-sized minerals will swell or shrink depending on the soil 

31 water content;

32

33 (d) Soil depth;

34

35 (e) Soil porosity;

36

37 (f) Bulk density (oven-dry mass density or wet mass density and associated 

38 water content);

39

40 (g) Soil chemistry;

41

42 (h) Permeability or saturated hydraulic conductivity; and

43

44 (i) Soil strength—typically the shear strength.

45

46 The soil strength may be discussed in more detail in sections addressing geotechnical 

47 properties (see Section 2.6 of this SRP).

48
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1 2.5.4 Evaluation Findings

2

3 If the staff determines that no license conditions are required for the applicant’s description of 

4 soil because the applicant or licensee provided adequate and complete information that fully 

5 addresses all relevant regulatory requirements, typically a single paragraph is sufficient for the 

6 evaluation findings section. Begin the section with the sentence: “NRC staff has completed its 

7 review of the applicant’s description of soil at the conventional uranium mill or heap leach facility 

8 in accordance with Section 2.5.3 of the standard review plan.” Following this sentence, state 

9 what information the applicant provided in the application. As discussed in the introduction 

10 of this SRP, a bullet list or sentence format may be used to list what information the applicant 

11 has provided. 

12

13 After the description of the information the applicant provided, the following or a similar

14 statement can be added: “Based on the review conducted by NRC staff, the information 

15 provided in the application meets the applicable acceptance criteria of Section 2.5.3 of the 

16 standard review plan. Therefore, NRC staff concludes that the applicant’s description of soil is 

17 acceptable and is in compliance with 10 CFR 40.31(h), which requires completeness and 

18 accuracy of information; 10 CFR Part 40, Appendix A, Criterion 1, which requires isolation of 

19 tailings and associated contaminants; and 10 CFR Part 40, Appendix A, Criterion 5G(2), which 

20 requires providing characteristics of underlying soils in support of a tailings disposal system 

21 proposal.” As a concluding statement, indicate the reason why the applicant’s information is 

22 considered adequate and complete, and why or how that information complies with the 

23 identified regulatory requirements.

24

25 If license conditions are needed, then a more detailed discussion is typically required. Begin 

26 this section with the sentence: “NRC staff has completed its review of the applicant’s 

27 description of soil at the conventional uranium mill or heap leach facility in accordance with 

28 Section 2.5.3 of the standard review plan.” Following this sentence, state what information the 

29 applicant provided in the application, including identification of the information that was omitted 

30 or inadequate. As discussed in the introduction of this SRP, a bullet list or sentence format may 

31 be used to list what information the applicant has provided. Next, state why a license condition 

32 is needed, followed by the license condition or conditions. 

33

34 In a separate paragraph following the discussion of the required license condition(s), include the 

35 statement: “Based on the review conducted by NRC staff, the information provided in the 

36 application, supplemented by provisions of the license condition(s) discussed above, meets the 

37 applicable acceptance criteria of Section 2.5.3 of the standard review plan. Therefore, NRC 

38 staff concludes that the applicant’s description of soil is acceptable and is in compliance with 

39 10 CFR 40.31(h), which requires completeness and accuracy of information; 10 CFR Part 40, 

40 Appendix A, Criterion 1, which requires isolation of tailings and associated contaminants; and 

41 10 CFR Part 40, Appendix A, Criterion 5G(2), which requires providing characteristics of 

42 underlying soils in support of a tailings disposal system proposal.” If not discussed in the 

43 preceding paragraph(s), include a statement or summation as to why or how the application and 

44 license condition(s) jointly comply with the identified regulatory requirements.

45

46 2.5.5 Reference

47

48 Dane, J.H. and G.C. Topp, eds. “Methods of Soil Analysis: Part 4 Physical Methods.” 

49 Madison, Wisconsin: Soil Science Society of America, Inc. 2002.

50
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1 2.6 Geotechnical

2

3 2.6.1 Areas of Review 

4

5 Staff should examine information in the license application on the geotechnical aspects of the 

6 site geography and stratigraphy and geotechnical characteristics of the proposed surface

7 impoundments and associated substructure materials. In addition, staff should examine 

8 geotechnical characteristics of materials used to provide stabilization, including borrow-area 

9 material characteristics. The staff should also examine exploration data; the description of 

10 physical and chemical properties; sampling and laboratory and/or field measurement 

11 techniques; and test results with interpretation, including static and dynamic properties of the 

12 materials. This review should be coordinated with the review of geological, stratigraphical, and 

13 seismological information, as described in Section 2.4 of this SRP.

14

15 2.6.2 Review Procedures

16

17 The geotechnical site characterization information constitutes part of the input data needed for 

18 analysis and design of the conventional uranium mill or heap leach facilities. The review should 

19 focus on the appropriateness of the geotechnical site characterization for the proposed 

20 conventional uranium mill or heap leach facility, including the determination of whether 

21 appropriate characterization methods are properly used. The reviewer should use the following 

22 procedures when reviewing the geotechnical characterization of the conventional uranium mill

23 or heap leach facility:

24

25 (1) Ensure that the applicant has described the stratigraphy of sites for mill buildings, 

26 surface impoundment(s), and/or the heap leach facilities. This information should meet,

27 in part, the requirements of 10 CFR Part 40, Appendix A, Criterion 5G(2).

28

29 (2) Ensure that the applicant has described the stratigraphy of the site for borrow areas

30 designated to be used for construction of the surface impoundment(s). This information 

31 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 5G(2).

32

33 (3) Ensure that the applicant has adequately described the sampling program(s) to obtain 

34 samples and used appropriate laboratory and field tests to adequately characterize the 

35 geotechnical properties of the tailings, leachable ores, borrow materials, materials 

36 underlying the site, and other materials to be used. For a new conventional uranium 

37 mill, properties of the tailings may be estimated. Verify that the applicant has provided 

38 adequate technical justification for selecting these estimated property values. This 

39 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A,

40 Criterion 5G(2).

41

42 (4) Ensure that the physical and engineering properties of the tailings, leachable ore, 

43 underlying materials at the site(s), borrow materials, and other materials have been 

44 properly presented. This information should meet, in part, the requirements of 

45 10 CFR Part 40, Appendix A, Criterion 5G(2).

46

47 The reviewer should evaluate methods used to characterize the site to ensure that they comply 

48 with generally accepted standards, such as those of the American Society for Testing and 

49 Materials (ASTM International) and those commonly used in the geotechnical engineering 

50 profession. Areas to be examined in this respect include the in situ and laboratory testing 
Site Characterization

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1 programs, sampling techniques, and analyses for determining the physical and engineering 

2 properties of materials at the site. Field investigations and laboratory testing procedures 

3 generally not used in the geotechnical engineering profession should be reviewed in 

4 greater detail.

5

6 2.6.3 Acceptance Criteria

7

8 The geotechnical site characterization is acceptable if it provides the needed input for the 

9 design and analysis of these facilities and meets the following criteria:

10

11 (1) The description of the stratigraphy provides detailed information about the extent, 

12 thickness, uniformity, shape, and orientation of the underlying strata at the surface

13 impoundment(s). The description includes, but is not limited to:

14

15 (a) Information obtained from borings, test pits, and other surface- and 

16 subsurface-based surveying methods;

17

18 (b) Information included in both geological and geophysical logs;

19

20 (c) Information obtained using techniques that can detect significant 

21 discontinuities, fractures (e.g., faults), and channels of deposits with high 

22 hydraulic conductivity; and

23

24 (d) Information that has been collected from a sufficient number of locations to 

25 provide adequate spatial coverage.

26

27 (2) The stratigraphy of the borrow areas for materials to be used in constructing the radon 

28 barrier, cover, and any embankments for the surface impoundment(s) has been 

29 described in detail. The description includes both geological and 

30 geophysical techniques to delineate the extent of available materials and establish 

31 their characteristics.

32

33 (3) Sampling scopes and sample collection techniques conducted to obtain laboratory 

34 samples and laboratory and field tests selected to characterize or estimate geotechnical 

35 properties of the tailings, leachable ores, borrow materials, materials underlying the 

36 site, and other materials to be used are appropriate and follow acceptable standards 

37 (e.g., regulatory guides, appropriate standards published by ASTM International, and the 

38 suggested methods published by the International Society for Rock Mechanics). The 

39 sample collection program(s) provide adequate spatial coverage and are sufficient to 

40 ensure that samples collected are representative of the range of in-situ soil and rock 

41 conditions taking into consideration the associated variabilities within the site. If 

42 standard procedures are not used, a detailed discussion of the sample preparation, 

43 testing conditions, testing technique, and data interpretation, in addition to the 

44 justification of the testing method, is presented. The applicant has provided adequate 

45 technical justification for the appropriateness of estimated properties of the mill tailings.

46

47 Locations of soils and rocks that may be unsuitable due to their physical or chemical 

48 properties are appropriately identified and documented.

49

50 Laboratory and field tests used to characterize the soil and rock are appropriate and are 

51 consistent with guidance. Regulatory Guide 1.132, “Site Investigations for Foundations 
Site Characterization

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1 of Nuclear Power Plants,” Revision 2 (NRC, 2003a) and Regulatory Guide 1.138, 

2 “Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of 

3 Nuclear Power Plants,” Revision 2 (NRC, 2003b, Appendix A) contain acceptable 

4 testing techniques for investigating a particular property both in situ and in a 

5 laboratory, respectively.

6

7 (4) Physical and engineering properties of the tailings, leachable ore, underlying materials at 

8 the site(s), borrow materials, and other materials determined from laboratory and field 

9 tests are properly presented using appropriate plots and graphs. The parameters for 

10 evaluation of heap leach operations, mill tailings, borrow materials, other materials, and 

11 underlying soil and rock include, but are not limited to, the following:

12

13 (a) Estimated or measured size distribution of mill tailings, leachable ore, and 

14 borrow materials;

15

16 (b) Strength of soil and rock underneath the surface impoundments in addition to 

17 tailings and heap leach materials including potential loss of shear strength 

18 resulting from strain softening;

19

20 (c) Soil and geomembrane liner interface strength, if geomembrane liner is to be 

21 used as a liner component;

22

23 (d) Compressibility and rate of consolidation of tailings or heap leach ore;

24

25 (e) Permeability of mill tailings and ore particles for heap leach;

26

27 (f) Swelling and shrinkage of cover materials;

28

29 (g) Liquefaction potential of mill tailings and ore particles on heap leach pads; and

30

31 (h) Long-term moisture content for radon barrier material.

32

33 The information is sufficient to provide the required input for the design of the facility and to 

34 enable the reviewer to assess compliance with the regulatory requirements, such as site 

35 features contributing to waste isolation; facility location with respect to an active fault; and 

36 reasonable assurance of control of radiological hazards to be effective for 1,000 years to the 

37 extent reasonably achievable, and in any case, for at least 200 years.

38

39 2.6.4 Evaluation Findings

40

41 If the staff determines that no license conditions are required for geotechnical aspects because 

42 the applicant or licensee provided adequate and complete information that fully addresses all 

43 relevant regulatory requirements, typically a single paragraph is sufficient for the evaluation 

44 findings section. Begin the section with the sentence: “NRC staff has completed its review of 

45 the applicant’s description of geotechnical aspects at the conventional uranium mill or heap 

46 leach facility in accordance with Section 2.6.3 of the standard review plan.” Following this 

47 sentence, state what information the applicant provided in the application. As discussed in the 

48 introduction of this SRP, a bullet list or sentence format may be used to list what information the 

49 applicant has provided. 

50
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1 After the description of the information the applicant provided, the following or a similar

2 statement can be added: “Based on the review conducted by NRC staff, the information 

3 provided in the application meets the applicable acceptance criteria of Section 2.6.3 of the 

4 standard review plan. Therefore, NRC staff concludes that the applicant’s description of 

5 geotechnical aspects is acceptable and is in compliance with 10 CFR Part 40, Appendix A, 

6 Criterion 5G(2), relating to the permeability characteristics of the site.” As a concluding 

7 statement, indicate the reason why the applicant’s information is considered adequate and 

8 complete, and why or how that information complies with the identified regulatory requirements.

9

10 If license condition(s) are needed, then a more detailed discussion is typically required. Begin 

11 this section with the sentence: “NRC staff has completed its review of the applicant’s 

12 description of geotechnical aspects at the conventional uranium mill or heap leach facility in 

13 accordance with Section 2.6.3 of the standard review plan.” Following this sentence, state what 

14 information the applicant provided in the application, including identification of the information 

15 that was omitted or inadequate. As discussed in the introduction of this SRP, a bullet list or 

16 sentence format may be used to list what information the applicant has provided. Next, state 

17 why a license condition is needed, followed by the license condition or conditions. 

18

19 In a separate paragraph following the discussion of the required license condition(s), include the 

20 statement: “Based on the review conducted by NRC staff, the information provided in the 

21 application, supplemented by provisions of the license condition(s) discussed above, meets the 

22 applicable acceptance criteria of Section 2.6.3 of the standard review plan. Therefore, NRC 

23 staff concludes that the applicant’s description of geotechnical aspects is acceptable and is in 

24 compliance with 10 CFR Part 40, Appendix A, Criterion 5G(2), relating to the permeability 

25 characteristics of the site.” If not discussed in the preceding paragraph(s), include a statement

26 or summation as to why or how the application and license condition(s) jointly comply with the 

27 identified regulatory requirements.

28

29 2.6.5 References

30

31 NRC. Regulatory Guide 1.132, “Site Investigations for Foundations of Nuclear Power Plants.” 

32 Rev. 2. Washington, DC: U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory 

33 Research. 2003a.

34

35 ––––. Regulatory Guide 1.138, “Laboratory Investigations of Soils and Rocks for Engineering 

36 Analysis and Design of Nuclear Power Plants.” Rev. 2. Washington, DC: U.S. Nuclear 

37 Regulatory Commission, Office of Nuclear Regulatory Research. 2003b. 

38

39 2.7 Hydrology

40

41 2.7.1 Groundwater Hydrology—Regional and Site Specific 

42

43 2.7.1.1 Areas of Review

44

45 Characterization of the regional and site-specific groundwater hydrology at conventional 

46 uranium mill or heap leach facilities must be sufficient to assess potential effects of conventional 

47 uranium mill or heap leach operations on the uppermost aquifer (as defined in Section 2.2.3 of 

48 this SRP), where regulatory compliance is to be evaluated. The areas of review include:

49

50 (1) The description of regional and local (site-specific) groundwater hydrology;
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1 (2) The assessment of available groundwater resources and groundwater quality within the 

2 proposed facility boundaries and adjacent properties; and

3

4 (3) The assessment of the potential effect of pumping to groundwater drawdown in the 

5 uppermost aquifer, if the groundwater in the uppermost aquifer is pumped for 

6 consumptive water use during construction, operation, and site reclamation.

7

8 2.7.1.2 Review Procedures

9

10 Staff should use the following procedures when conducting the review of regional and 

11 site-specific groundwater hydrology:

12

13 (1) Review available data from well logs, hydrologic tests, and measurements to obtain 

14 confidence that sufficient hydrological data have been collected at the conventional 

15 uranium mill or heap leach facility, and at proposed locations for surface impoundments,

16 and that the data support the applicant’s hydrologic conceptual model for groundwater 

17 flow in the uppermost aquifer beneath the proposed facility and surface impoundments. 

18 This information should meet, in part, the requirements of 10 CFR 40.31(h) and

19 10 CFR Part 40, Appendix A, Criterion 5G(2).

20

21 (a) Verify that the applicant used acceptable techniques for groundwater-level 

22 measurements in the uppermost aquifer. Verify that the applicant adequately 

23 presented groundwater levels, hydraulic gradients, groundwater flow directions, 

24 and groundwater recharge zones and rates for the uppermost aquifer beneath 

25 the proposed facility. 

26

27 (b) Review the applicant’s assessment of seasonal and historical variations of 

28 groundwater levels in the uppermost aquifer. 

29

30 (c) Verify that the unsaturated zone between the ground surface and the uppermost 

31 aquifer is properly characterized. Verify that the applicant identifies perched 

32 zones beneath the proposed site above the uppermost aquifer, if they exist. 

33 Note that the saturated zone created by conventional uranium mill or heap leach 

34 operations (through accidental water seepage or leakage from the operation site 

35 or surface impoundments) would not be considered to be an aquifer unless the 

36 zone is, or potentially is (i) hydraulically interconnected to a natural aquifer, 

37 (ii) capable of discharge to surface water, or (iii) reasonably accessible 

38 because of migration beyond the vertical projection of the boundary of the 

39 land transferred for long-term government ownership and care in accordance 

40 with 10 CFR Part 40, Appendix A, Criterion 11.

41

42 (d) Verify that the zones of water exchanges between surface water bodies and the 

43 uppermost aquifer are identified.

44

45 (e) Review the adequacy of local groundwater sources (from shallow or deep 

46 aquifers) for use, and determine whether a limiting extraction rate would avoid 

47 dewatering of the uppermost aquifer if the consumptive water use during 

48 operations or site reclamation is supplied locally from the uppermost aquifer 

49 beneath the proposed facility.

50
Site Characterization

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1 (2) Verify that the number and location of boreholes are sufficient to support the hydrologic 

2 characterization, if shown as such in the cross sections. This part of the review should 

3 be coordinated with the review of Section 2.4 of this SRP. This information should 

4 meet, in part, the requirements of 10 CFR 40.31(h) and 10 CFR Part 40, Appendix A, 

5 Criterion 5G(2).

6

7 (3) Determine whether hydraulic properties for the uppermost aquifer and its underlying

8 confinement are determined using appropriate methods (e.g., aquifer pumping tests, 

9 slug tests) and whether the methods or standards used to analyze the field test data are 

10 properly described and referenced. If the confining layer below the uppermost aquifer is 

11 absent or ineffective, and if the uppermost aquifer is not hydraulically isolated from 

12 underlying deep major aquifers, determine whether the hydraulic properties of underlying 

13 major aquifers are also determined using appropriate methods. This information should 

14 meet, in part, the requirements of 10 CFR 40.31(h) and 10 CFR Part 40, Appendix A, 

15 Criterion 5G(2). 

16

17 (4) Evaluate whether the applicant has developed an acceptable conceptual model of the 

18 groundwater hydrology at the proposed site and whether the conceptual model is 

19 adequately supported by the site characterization data. This information should meet, in 

20 part, the requirements of 10 CFR 40.31(h); 10 CFR 40.41(c); and 10 CFR Part 40, 

21 Appendix A, Criterion 5G(2).

22

23 (5) Verify that the applicant identified sources, uses (e.g., domestic, irrigation, livestock), 

24 and quality of groundwater, along with locations of existing groundwater supply wells at 

25 and near the site. This information should meet, in part, the requirements of 

26 10 CFR Part 40, Appendix A, Criteria 5B(4) and 5G(3).

27

28 (6) Evaluate the applicant’s assessment of the potential interference of other nearby mining, 

29 and mineral or resource recovery activities to the groundwater hydrology at the proposed 

30 site (e.g., changes in water quality, flow rates and directions in the uppermost aquifer). 

31 This information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

32 Criterion 5G(2).

33

34 (7) Evaluate the applicant’s groundwater simulation model, if available. It should be noted 

35 that groundwater simulation model is not required as part of license application, but the 

36 applicant may choose to use simulation models to support their site-specific 

37 hydrogeologic conceptual model and to demonstrate how they chose the locations and 

38 spacing of compliance and other groundwater monitoring wells. If the numerical 

39 simulation model is submitted as part of the license application, verify that the applicant 

40 validated its groundwater simulation model using field data (e.g., groundwater levels, 

41 flow directions, and hydraulic gradients) acquired in different seasons including high 

42 and low recharge periods. This information should meet, in part, the requirements of

43 10 CFR 40.31(h).

44

45 2.7.1.3 Acceptance Criteria

46

47 The characterization of the regional and site-specific groundwater hydrology is acceptable if it

48 meets the following criteria: 

49

50 (1) The applicant has described the local and regional hydraulic gradient and 

51 hydrostratigraphy in sufficient detail using data from well logs, hydrologic tests, and 
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1 measurements, and data from other sources, as described in Section 2.1.3(3) of this 

2 SRP. The applicant’s description of groundwater hydraulic gradients, horizontal 

3 hydraulic conductivity, the thickness of the uppermost aquifer, the thickness and vertical 

4 hydraulic conductivity of the lower confinement of the uppermost aquifer, outcrop areas,

5 and areal extent of the uppermost aquifer is consistent with the applicant’s conceptual 

6 hydrogeologic model.

7

8 (a) The applicant has shown that groundwater-level measurements are collected by 

9 acceptable methods, such as ASTM D4750–87 (ASTM International, 2001). 

10 Potentiometric maps or separate maps and/or tables present groundwater 

11 elevations and hydraulic gradient data. These maps provide two levels of details:

12 (i) the regional map represents the groundwater elevations and areal extent of 

13 the uppermost aquifer and encompasses the likely consequences on any 

14 affected highly populated areas; and (ii) the local (site-scale) map encompasses 

15 groundwater elevations and the extent of the uppermost aquifer within the 

16 proposed area. Potentiometric maps clearly show the locations of the wells and 

17 boreholes used to determine the groundwater surface elevations. The depths 

18 and screened intervals of the wells and boreholes are provided on cross sections 

19 and/or in tables. The contour interval of potentiometric maps is sufficient to 

20 clearly show the groundwater flow direction in the uppermost aquifer. The 

21 number of boreholes and wells, where groundwater surface elevation 

22 measurements were taken, is sufficient to determine hydraulic gradients and 

23 groundwater flow directions in the uppermost aquifer. A reasonable effort has 

24 been made to consider as many existing wells and boreholes as possible in 

25 constructing regional and groundwater potentiometric maps.

26

27 (b) The applicant has provided an assessment of the seasonal and historical 

28 variability of groundwater elevations and hydraulic gradients in the uppermost 

29 aquifer based on either data the applicant collected onsite or acquired from 

30 different sources, as described in Section 2.1.3 of this SRP. The applicant also 

31 provided an assessment of the seasonal and historical variability of the depth to 

32 groundwater levels in the uppermost aquifer from ground surface and an 

33 assessment of infiltration rates and distributions to the uppermost aquifer.

34

35 (c) The applicant has provided an adequate hydrogeologic description of the 

36 unsaturated zone extending from ground surface to the uppermost aquifer, 

37 including an assessment of potential preferential pathways (e.g., buried stream 

38 channels, sinkholes, or abandoned wells). If local perched zones (i.e., isolated 

39 and disconnected fully saturated zones) above the uppermost aquifer exist, the 

40 applicant noted their presence. Such perched zones may cause contaminated 

41 water to be diverted around monitoring systems or may be improperly interpreted 

42 as the uppermost aquifer. The applicant has distinguished naturally occurring

43 perched aquifers from potentially temporarily formed perched zones during 

44 uranium milling and heap leach operations below the proposed facility.

45

46 (d) The applicant has adequately identified hydraulic connections and water 

47 exchange zones between the uppermost aquifers and surface waters. If such 

48 groundwater–surface water exchange zones exist, the applicant provided an 

49 estimate for the direction and flux rate of water exchanges by presenting 

50 seasonal variations in the groundwater elevations in the uppermost aquifer and 

51 the stream stage along the zone of hydraulic connections between the 
Site Characterization

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1 uppermost aquifers and surface waters. The direction and flux rate water 

2 exchanges between a hydraulically connected uppermost aquifer and surface 

3 waters are important for the assessment of potential contaminant and mass 

4 transfer between surface waters and groundwater due to proposed actions.

5

6 (e) The applicant has identified sources for consumptive water use during 

7 construction, operations, and reclamation at the proposed conventional uranium 

8 mill or heap leach site. If the consumptive water use is to be supplied partly or 

9 entirely from the uppermost aquifer beneath the facility, the applicant has 

10 provided an estimate for the consumptive water use from the uppermost aquifer 

11 during construction, operation, and reclamation. The applicant has also provided 

12 an assessment of the potential impacts of consumptive water use from the 

13 uppermost aquifer on the quality and quantity (in terms of drawdown) of 

14 groundwater in the uppermost aquifer within the proposed facility boundaries and 

15 adjacent properties. 

16

17 (2) The applicant has provided adequate hydrological cross sections for illustrating the 

18 interpreted hydrostratigraphy. For large or hydrologically complex areas, more than one 

19 cross section may be necessary. These cross sections have been constructed for the 

20 area within the proposed facility boundary such that they cut through the operational 

21 area, milling buildings, surface impoundments, and other critical locations. The cross 

22 sections identified continuity and thickness of the uppermost aquifer, its underlying 

23 confinement, major structural features (e.g., faults, folds, dikes), and groundwater levels. 

24 Cross sections are based on borehole data acquired during well installation or 

25 exploratory drilling. Significant borehole data are included in an appendix to the 

26 application. The information gathered on boreholes allows the identification of potential 

27 discontinuities and fractured zones in the uppermost aquifer and the underlying 

28 confinement, and potential channel deposits of high vertical conductivity above the 

29 uppermost aquifer beneath the surface impoundments. 

30

31 (3) The applicant has described hydraulic properties of the uppermost aquifer to estimate

32 potential migration paths and distribution of hazardous contaminants if they leak from 

33 surface impoundments during or after milling operations. The hydrological properties of 

34 aquifers include aquifer type, shape, extent, thickness, porosity, hydraulic conductivity, 

35 transmissivity, and storativity or storage coefficient. The hydrologic properties of the 

36 underlying confinement of the uppermost aquifer include vertical conductivity, continuity,

37 uniformity (e.g., jointed or fractured rock type), porosity, and thickness.

38

39 Hydraulic properties of the uppermost aquifer, next underlying aquifer and confining 

40 layers are determined using proper field tests (e.g., aquifer pumping tests, slug tests) for 

41 parameters such as hydraulic conductivity, transmissivity, and specific storage. Field 

42 tests are also designed to take into account the effects of faults and other geological and 

43 structural features. The field tests are designed to take into account the aquifer type

44 (e.g., unconfined, confined, leaky) of the uppermost aquifer. Appropriate methods are 

45 used to interpret aquifer properties from field test data. If aquifer pumping tests are 

46 used, appropriate methods include single-well drawdown and recovery tests, drawdown 

47 versus time in a single observation well, and drawdown versus distance pumping tests 

48 using multiple observation wells. The methods or standards used to analyze pumping 

49 test data are described and referenced; acceptable methods of analysis include use of 

50 curve fitting techniques for drawdown or recovery curves that are referenced to 

51 peer-reviewed journal publications, texts, or ASTM standards (ASTM International, 
Site Characterization

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1 2001). Where fitted curves deviate from measured drawdown, the applicant explains the 

2 probable cause of the deviation (e.g., leaky aquitards, delayed yield effects, boundary 

3 effects). For estimates of porosity, the applicant uses laboratory analysis of core 

samples, borehole geophysical methods, and/or analysis of the barometric efficiency3 4 of 

5 the aquifer (e.g., Lohman, 1972). The applicant distinguishes between total porosity 

6 estimated from borehole geophysical methods and effective porosity (excluding 

7 immobile zone porosity) that affects transport of chemical constituents. 

8

9 (4) The applicant has established an acceptable conceptual hydrological model for the 

10 conventional uranium mill or heap leach site and surrounding areas. The conceptual

11 model provides a framework for the applicant to make decisions on the optimal methods 

12 for uranium milling or heap leaching that minimize potential environmental and safety 

13 impacts. The applicant adequately incorporated data acquired onsite during site 

14 characterization, from the U.S. Geological Survey, or from other sources to support the 

15 conceptual hydrological model.

16

17 (5) The applicant has provided information on underground sources of drinking water and 

18 aquifers (e.g., the state groundwater classification at the proposed conventional uranium 

19 mill or heap leach facility). The applicant has adequately described:

20

21 (a) The types of present and projected (life of proposed facility) water uses

22 (e.g., domestic, irrigation, livestock) and descriptions of the methodology and 

23 sources used to develop projected water demands;

24

25 (b) The present and projected (life of facility) water use estimates for groundwater by 

26 types and rates, including present and projected withdrawal and descriptions of 

27 the methodology and sources used to develop water use projects; and

28

29 (c) The well depth, groundwater elevations, flow rates, drawdown, and descriptions 

30 of the uppermost aquifer for existing groundwater wells.

31

32 (6) The applicant has adequately assessed the potential interference of other nearby 

33 uranium recovery and/or other mineral or resource recovery to site groundwater 

34 hydrology. The applicant considered interferences including, but not limited to,

35 (i) groundwater drawdown in the uppermost aquifer beneath the proposed mill facility 

36 due to consumptive groundwater uses from the uppermost aquifer at nearby facilities or

37 (ii) groundwater contamination in the uppermost aquifer beneath the proposed mill 

38 facility due to artificial connection (through, for example, exploratory drills or abandoned 

39 mine shafts or pit mines) between the uppermost aquifer beneath the proposed mill 

40 facility and underlying major aquifers operated offsite for mineral and resources 

41 recoveries. This information provides the basis for evaluating potential effects of other 

42 nearby uranium or mineral resources recovery on local groundwater resources beneath 

43 the proposed site. The applicant has demonstrated that the effect of these additional 

44 activities can be differentiated from that caused by the conventional uranium mill or heap 

45 leach activities alone. The applicant used sufficient information to evaluate the potential 

46 effects, such as aquifer drawdown, artificial connections, and water quality.

47

48 (7) If a groundwater model is used for simulating site hydrogeology, model assumptions, 

49 inputs (e.g., flow domain geometry, hydraulic parameters, initial and boundary 

 3

The total porosity of the aquifer is the product of the specific storativity of the aquifer and the barometric efficiency.
Site Characterization

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1 conditions), calibration, and outputs are detailed. The model structure and model 

2 parameterization are consistent with the site hydrostratigraphy and the conceptual 

3 model. The model validation data are clearly identified, and the validation procedure is 

4 clearly presented. The model validation with field data is conducted for different 

5 seasons including high and low recharge (and hence, high and low infiltration) periods to 

6 build confidence in the model results. The model outputs are shown in graphic formats. 

7 If discontinuous structural features, such as faults and dikes, are present (as discussed 

8 in Section 2.4 of this SRP), such features are properly characterized into either barriers 

9 or conduits to fluid flows, the characterization is consistent with pumping tests, and 

10 faults are appropriately included as special features in the applicant’s groundwater 

11 simulation model.

12

13 2.7.1.4 Evaluation Findings

14

15 If the staff determines that no license conditions are required for the regional and site-specific 

16 groundwater hydrology information because the applicant or licensee provided adequate and 

17 complete information that fully addresses all relevant regulatory requirements, typically a single 

18 paragraph is sufficient for the evaluation findings section. Begin the section with the sentence: 

19 “NRC staff has completed its review of the regional and site-specific groundwater hydrology 

20 information at the conventional uranium mill or heap leach facility in accordance with 

21 Section 2.7.1.3 of the standard review plan.” Following this sentence, state what information the 

22 applicant provided in the application. As discussed in the introduction of this SRP, a bullet list or 

23 sentence format may be used to list what information the applicant has provided. 

24

25 After the description of the information the applicant provided, the following or a similar

26 statement can be added: “Based on the review conducted by NRC staff, the information 

27 provided in the application meets the applicable acceptance criteria of Section 2.7.1.3 of the 

28 standard review plan. Therefore, NRC staff concludes that the applicant’s regional and 

29 site-specific groundwater hydrology information is acceptable and is in compliance with 

30 10 CFR 40.31(h), which requires completeness and accuracy in all materials provided by an 

31 applicant;10 CFR 40.41(c), which requires confinement of possession and control over process 

32 fluids containing source and byproduct materials to the locations and purposes authorized in the 

33 license; 10 CFR Part 40, Appendix A, Criterion 5B(4), which requires identification of 

34 underground source of drinking water exempted aquifers; 10 CFR Part 40, Appendix A, 

35 Criterion 5G(2), which requires detailed information on the characteristics of the underlying soil 

36 and geological formation; 10 CFR Part 40, Appendix A, Criterion 5G(3), which requires

37 information on the location, extent, quality, capacity, and current uses of groundwater; and 

38 10 CFR Part 40, Appendix A, Criterion 11, which relates to ownership of tailings and their 

39 disposal sites.” As a concluding statement, indicate the reason why the applicant’s information 

40 is considered adequate and complete, and why or how that information complies with the 

41 identified regulatory requirements.

42

43 If license conditions are needed, then a more detailed discussion is typically required. 

44 Begin this section with the sentence: “NRC staff has completed its review of the regional and 

45 site-specific groundwater hydrology information at the conventional uranium mill or heap leach 

46 facility in accordance with Section 2.7.1.3 of the standard review plan.” Following this sentence, 

47 state what information the applicant provided in the application, including identification of the 

48 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

49 bullet list or sentence format may be used to list what information the applicant has provided. 

50 Next, state why a license condition is needed, followed by the license condition or conditions. 

51
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1 In a separate paragraph following the discussion of the required license condition(s), include the 

2 statement: “Based on the review conducted by NRC staff, the information provided in the 

3 application, supplemented by provisions of the license condition(s) discussed above, meets the 

4 applicable acceptance criteria of Section 2.7.1.3 of the standard review plan. Therefore, NRC 

5 staff concludes that the applicant’s regional and site-specific groundwater hydrology information 

6 is acceptable and is in compliance with 10 CFR 40.31(h) 10 CFR 40.41(c), which requires 

7 confinement of possession and control over process fluids containing source and byproduct 

8 materials to the locations and purposes authorized in the license; 10 CFR Part 40, Appendix A, 

9 Criterion 5B(4), which requires identification of underground source of drinking water exempted 

10 aquifers; 10 CFR Part 40, Appendix A, Criterion 5G(2), which requires detailed information on 

11 the characteristics of the underlying soil and geological formation; 10 CFR Part 40, Appendix A, 

12 Criterion 5G(3), which requires information on the location, extent, quality, capacity, and current 

13 uses of groundwater; and 10 CFR Part 40, Appendix A, Criterion 11, which relates to ownership 

14 of tailings and their disposal sites.” As a concluding statement, indicate the reason why the 

15 applicant’s information is considered adequate and complete. If not discussed in the preceding 

16 paragraph(s), include a statement or summation as to why or how the application and license 

17 condition(s) jointly comply with the identified regulatory requirements.

18

19 2.7.1.5 References

20

21 ASTM International. “Standard Test Method for Determining Subsurface Liquid Levels in a 

22 Borehole or Monitoring Well (Observation Well).” Test Method D4750–87 (Reapproved 2001). 

23 West Conshohocken, Pennsylvania: ASTM International. 2001. 

24

25 Lohman, S.W. “Ground-Water Hydraulics.” U.S. Geological Survey Professional Paper 708. 

26 Denver, Colorado: U.S. Geological Survey. 1972. 

27

28 2.7.2 Surface Water Hydrology—Regional and Site Specific

29

30 2.7.2.1 Areas of Review

31

32 Characterization of the regional and site-specific surface water hydrology at the conventional 

33 uranium mill or heap leach facility must be sufficient to properly assess isolation of surface

34 impoundments, to establish potential effects of conventional uranium mill or heap leach 

35 operations on surface waters, and to assess the potential effects of surface water flooding and 

36 erosion on the conventional uranium mill or heap leach facility. The areas of review include:

37

38 (1) Descriptions of surface water features in the site area including type (ephemeral or 

39 perennial), size, drainage area, jurisdictional status (e.g., U.S. Army Corps of 

40 Engineers), current and predicted future uses, permanency, pertinent hydrological or 

41 morphological characteristics, and their proximity to conventional uranium mill or heap 

42 leach processing plants, and surface impoundments or to other facilities that might be 

43 negatively affected by surface erosion or flooding;

44

45 (2) Assessment of the potential for erosion or flooding that may require special design 

46 features or mitigation measures to be implemented; and

47

48 (3) Assessment of typical seasonal ranges and averages and the historical extremes for 

49 levels and/or flow rates of surface water bodies.

50
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1 2.7.2.2 Review Procedures

2

3 Staff should use the following procedures when conducting the review of regional and 

4 site-specific surface water hydrology:

5

6 (1) Review surface water data, including maps that identify lakes, wetlands, springs, 

7 permanent and intermittent streams, rivers and creeks, surface drainage areas, and 

8 other surface water bodies within the proposed facility boundaries and adjacent 

9 properties. Review hydrographs of important surface water features within and 

10 adjacent to the site boundary. This information should meet, in part, the requirements 

11 of 10 CFR 40.31(h) and 10 CFR Part 40, Appendix A, Criterion 1.

12

13 (2) Examine the topographic contour map to determine whether the contour intervals 

14 and information included on the map are sufficient to show significant variations in 

15 site environs, important drainage gradients, and upstream rainfall catchment areas.

16 This information should meet, in part, the requirements of 10 CFR 40.31(h) and

17 10 CFR Part 40, Appendix A, Criteria 1, 4(a) and 4(b).

18

19 (3) Evaluate the applicant’s assessment of the potential for erosion or flooding. Information 

20 regarding acceptable models for use in calculating the design storm for a 1,000-year 

21 design life for large surface impoundments may be found in NUREG–1623, “Design of 

22 Erosion Protection for Long-Term Stabilization” (NRC, 2002). Review guidance for flood 

23 mitigation structures is provided in NUREG–1620 (NRC, 2003). Review any special 

24 engineering features used to mitigate or prevent negative impacts of surface erosion and 

25 flooding. This information should meet, in part, the requirements of10 CFR 40.31(h);

26 10 CFR 40.32(c); and 10 CFR Part 40, Appendix A, Criteria 1 and 4(f).

27

28 (4) Review the applicant’s assessment of seasonal and, if data are available, the 

29 historical variability for discharge rates and/or levels of surface water features, and 

30 ensure that sufficient time intervals have elapsed between measurements to allow 

31 assessment of seasonal variability. This information should meet, in part, the 

32 requirements of 10 CFR 40.31(h) and 10 CFR Part 40, Appendix A, Criterion 5B(6).

33

34 2.7.2.3 Acceptance Criteria 

35

36 The characterization of the regional and onsite surface water hydrology is acceptable if it meets 

37 the following criteria: 

38

39 (1) The applicant has characterized surface water bodies and drainages within the site 

40 boundary and affected surroundings. Maps and information provided in the application 

41 identify the location, size, shape, hydrologic characteristics, jurisdictional status, and 

42 water use types of surface water bodies (including lakes, wetlands, permanent and 

43 intermittent streams, rivers, creeks, springs) within the proposed facility boundaries and 

44 adjacent properties, upstream and downstream river control structures, proposed 

45 diversion channels, upstream catchment areas, and surface drainage areas near the 

46 proposed facilities. The scale and clarity of the site topographic maps are adequate to 

47 conduct the necessary safety reviews.

48

49 The applicant has provided unit hydrographs (with tabulated values) for running surface 

50 water features within and upgradient of the proposed facility. The unit hydrographs

51 indicate the response of a basin or watershed, in terms of discharge or stage, to 1 cm 
Site Characterization

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1 [0.4 in] of excess rainfall occurring over the basin at a uniform rate for a specified 

2 duration (in terms of hours). The unit hydrograph can be used to estimate the direct 

3 runoff and stream flow (and hence to assess potential flooding and erosion impacts)

4 from arbitrary rainfall or storm events. 

5

6 (2) The choice of contour intervals and the locations of drainage basins on a topographic 

7 map are adequate to identify the relationship between the site and surface drainage, and 

8 variations in the drainage gradient in the vicinity of the proposed conventional uranium 

9 mill or heap leach facility. The choice of contour intervals is adequate to show that the 

10 applicant has selected a site that minimizes upstream rainfall catchment areas. 

11

12 (3) The applicant has provided a comprehensive assessment of the potential for flooding,

13 erosion, and depositional zones that could affect the conventional uranium mill or heap 

14 leach facility and surface impoundments. The evaluation of flooding and erosion 

15 potential is consistent with available geomorphological and topographic data or analysis 

16 of paleodischarge information. The applicant has provided inundation maps (e.g., for 

17 10 years, 100 years) for the major stream and creeks within and near the proposed 

18 facilities. In flood-prone areas, the applicant has conducted surface water and erosion 

19 modeling to assess the potential for erosion or flooding. The applicant has described 

20 acceptable flood mitigation and erosion protection measures (included proposed 

21 engineering structures) against the effects of flooding from nearby streams and for 

22 drainage and diversion channels. Erosion protection for drainage and diversion 

23 channels, including channel outlets, has been provided. If the applicant uses surface 

24 water or erosion modeling, acceptable models and input parameters have been used 

25 in the flood analyses and the resulting flood forces were acceptably accommodated in 

26 the design of surface impoundments and diversion channels or other onsite flood 

27 mitigation measures.

28

29 The applicant has adequately demonstrated the probable maximum precipitation 

30 potential and resulting runoff for site drainage and for drainage areas adjacent to the 

31 site. The probable maximum precipitation/probable maximum flood event is consistent 

32 with NUREG–1623 (NRC, 2002, Appendix D). In determining a local probable maximum 

33 precipitation event:

34

35 (a) The applicant has provided adequate support for values of the 1-hour, 6-hour, 

36 and 12-hour probable maximum precipitation events, as applicable.

37

38 (b) The applicant has demonstrated that appropriate values of infiltration have 

39 been selected.

40

41 (c) The applicant has demonstrated that appropriate methods (i.e., depending on the 

42 slope, configuration) have been selected. The U.S. Nuclear Regulatory 

43 Commission (NRC) staff independently verified that the methods selected 

44 compare reasonably well with various velocity-based methods.

45

46 (d) The applicant has demonstrated the rainfall distributions (particularly the 21⁄2-, 5-, 

47 and 15-minute distributions), and NRC staff has verified that the distributions are 

48 consistent with the distributions suggested in NUREG–1623 (NRC, 2002, 

49 Appendix D).

50
Site Characterization

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1 The applicant has demonstrated that the design of diversion channels in critical areas is 

2 consistent with guidance presented in NUREG–1623 (NRC, 2002, Appendix D). For the 

3 main channel area, appropriate models and input parameters have been used to design 

4 the erosion protection. The applicant has demonstrated that flow rates, flow depths, and 

5 flow shear stresses have been correctly computed. For the channel side slopes, the 

6 applicant has demonstrated that the side slopes are capable of resisting flow velocities 

7 and shear stresses from flows that occur directly down the side slope. This occurs often 

8 when diversion channels are constructed perpendicular to natural gullies (which 

9 discharge into the diversion channel). The shear forces in these locations often greatly 

10 exceed the forces produced by flows in the channel, particularly when the slope of the 

11 natural ground in the area is greater than the slope of the diversion channel.

12

13 For the outlet of the diversion channel, the applicant adequately addressed erosion in 

14 the discharge area. The applicant evaluated designs, similar to apron/toe designs, to 

15 determine their resistance to erosion. NUREG–1623 (NRC, 2002, Appendix D) 

16 discusses acceptable methods for designing channel outlets.

17

18 For the entire length of the diversion channel, the applicant discussed the effects of

19 sediment accumulations on flow velocities, channel capacity, and need for increased

20 rock size. The applicant has demonstrated that designs in which steep natural 

21 streams discharge into relatively flat diversion channels will not greatly increase

22 the potential for blockage of the channel due to sedimentation, consistent with

23 NUREG–1623 (NRC, 2002, Appendix E).

24

25 (4) The applicant has provided an assessment of seasonal and historical variability for 

26 discharge rates and/or water levels in surface water bodies. This assessment included

27 discharge rates and/or water levels over at least 1 year and collected periodically to 

28 represent seasonal variability. The applicant has provided minimum, maximum, and 

29 average flow rates and/or water levels for the surface bodies. The applicant has 

30 adequately explained interrupted measurements during discontinuity in water level and 

31 discharge data.

32

33 2.7.2.4 Evaluation Findings

34

35 If the staff determines that no license conditions are required for the regional and onsite surface 

36 water hydrology characterization because the applicant or licensee provided adequate and 

37 complete information that fully addresses all relevant regulatory requirements, typically a single 

38 paragraph is sufficient for the evaluation findings section. Begin the section with the sentence: 

39 “NRC staff has completed its review of the regional and onsite surface water hydrology 

40 characterization at the conventional uranium mill or heap leach facility in accordance with 

41 Section 2.7.2.3 of the standard review plan.” Following this sentence, state what information the 

42 applicant provided in the application. As discussed in the introduction of this SRP, a bullet list or 

43 sentence format may be used to list what information the applicant has provided. 

44

45 After the description of the information the applicant provided, the following or a similar

46 statement can be added: “Based on the review conducted by NRC staff, the information 

47 provided in the application meets the applicable acceptance criteria of Section 2.7.2.3 of the 

48 standard review plan. Therefore, NRC staff concludes that the applicant’s regional and 

49 onsite surface water hydrology characterization is acceptable and is in compliance with 

50 10 CFR 40.31(h), which requires completeness and accuracy in all materials provided by a 

51 applicant; 10 CFR 40.32(c), which requires that the applicant’s proposed equipment and 
Site Characterization

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1 procedures are adequate to protect public health; 10 CFR Part 40, Appendix A, Criterion 1, 

2 which requires permanent isolation of tailings and associated contaminants during siting 

3 decisions; 10 CFR Part 40, Appendix A, Criterion 4(a), which requires that upstream catchment 

4 areas be minimized; 10 CFR Part 40, Appendix A, Criterion 4(b), which requires that 

5 topographic features should provide good wind protection; 10 CFR Part 40, Appendix A, 

6 Criterion 4(f), which requires consideration of features that will promote deposition in the design 

7 of surface impoundments; and 10 CFR Part 40, Appendix A, Criterion 5B(6), which requires

8 consideration of the adverse effects of a conventional uranium mill or heap leach facility on the 

9 quality of surface waters.” As a concluding statement, indicate the reason why the applicant’s 

10 information is considered adequate and complete, and why or how that information complies 

11 with the identified regulatory requirements.

12

13 If license conditions are needed, then a more detailed discussion is typically required. Begin 

14 this section with the sentence: “NRC staff has completed its review of the regional and onsite 

15 surface water hydrology characterization at the conventional uranium mill or heap leach facility 

16 in accordance with Section 2.7.2.3 of the standard review plan.” Following this sentence, state 

17 what information the applicant provided in the application, including identification of the 

18 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

19 bullet list or sentence format may be used to list what information the applicant has provided. 

20 Next, state why a license condition is needed, followed by the license condition or conditions. 

21 In a separate paragraph following the discussion of the required license condition(s), include the 

22 statement: “Based on the review conducted by NRC staff, the information provided in the 

23 application, supplemented by provisions of the license condition(s) discussed above, meets the 

24 applicable acceptance criteria of Section 2.7.2.3 of the standard review plan. Therefore, NRC 

25 staff concludes that the applicant’s regional and onsite surface water hydrology characterization 

26 is acceptable and is in compliance with 10 CFR 40.31(h), which requires completeness and 

27 accuracy in all materials provided by a applicant; 10 CFR 40.32(c), which requires that the 

28 applicant’s proposed equipment and procedures are adequate to protect public health; 

29 10 CFR Part 40, Appendix A, Criterion 1, which requires permanent isolation of tailings and 

30 associated contaminants during siting decisions; 10 CFR Part 40, Appendix A, Criterion 4(a), 

31 which requires that upstream catchment areas be minimized; 10 CFR Part 40, Appendix A, 

32 Criterion 4(b), which requires that topographic features should provide good wind protection; 

33 10 CFR Part 40, Appendix A, Criterion 4(f), which requires consideration of features that will 

34 promote deposition in the design of surface impoundments; and 10 CFR Part 40, Appendix A, 

35 Criterion 5B(6), which requires consideration of the adverse effects of a conventional uranium 

36 mill or heap leach facility on the quality of surface waters.” If not discussed in the preceding 

37 paragraph(s), include a statement or summation as to why or how the application and license 

38 condition(s) jointly comply with the identified regulatory requirements.

39

40 2.7.2.5 References

41

42 NRC. NUREG–1620, “Standard Review Plan for the Review of a Reclamation Plan for Mill 

43 Tailings Sites Under Title II of the Uranium Mill Tailings Radiation Control Act of 1978.” Rev. 1. 

44 Washington, DC: U.S. Nuclear Regulatory Commission. June 2003.

45

46 –––––. NUREG–1623, “Design of Erosion Protection for Long-Term Stabilization.” Rev. 1. 

47 Washington, DC: U.S. Nuclear Regulatory Commission. August 2002.

48

49
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1 2.8 Preoperational Monitoring

2

3 2.8.1 Radiological Preoperational Monitoring

4

5 2.8.1.1 Areas of Review 

6

7 The reviewer should examine site-specific radiological data provided in the application including 

8 the results of measurements of radioactive materials occurring in soil, air, and in surface water 

9 and groundwaters that could be affected by the proposed operations. The reviewer should 

10 examine the design of the preoperational monitoring program, including which radionuclides are 

11 analyzed, sampling locations, sample type, sampling frequency, location and density of 

12 monitoring stations, the detection limits, and analytical methods used (see SRP Section 4.7.3).

13

14 An acceptable preoperational monitoring program includes air sampling (both particulate and 

15 radon); water sampling (groundwater and surface water); sampling of vegetation, food, and fish; 

16 soil and sediment sampling; direct radiation measurements; and radon flux. The preoperational 

17 monitoring program should include at least 12 consecutive months of data as identified in 

18 Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium Mills,”

19 (NRC, 1980, Revision 1). Complete soil sampling, direct radiation, and radon flux data should 

20 be completed prior to major site construction. It should be recognized that some samples may 

21 not be collected due to weather conditions, seasonal availability, or access to an area. For 

22 minimizing the number of potential requests for additional information, it is recommended that 

23 the data be collected before submittal of an application.

24

25 2.8.1.2 Review Procedures

26

27 The reviewer should use the following procedure when conducting the review of the 

28 preoperational monitoring program:

29

30 (1) Review the preoperational monitoring program to verify that it establishes preoperational 

31 conditions. Verify that the preoperational monitoring program is in accordance with the 

32 guidance provided in Regulatory Guide 4.14 (NRC, 1980, Revision 1, Table 1), including 

33 sampling frequency, sampling methods, and sampling location and density. Verify that 

34 soil sampling is conducted to a depth of 5 cm [2 in] in accordance with Regulatory 

35 Guide 4.14 (NRC, 1980, Revision 1), and to a depth of 15 cm [6 in] for preoperational

36 decommissioning data. The information reviewed in this procedure should meet, in part, 

37 the requirements of 10 CFR Part 40, Appendix A, Criterion 7.

38

39 For license renewals and amendment applications, Appendix A to this SRP provides guidance 

40 for examining facility operations and the approach that should be used in evaluating 

41 amendments and renewal applications.

42

43 2.8.1.3 Acceptance Criteria 

44

45 The preoperational monitoring program is acceptable if it meets the following criteria:

46

47 (1) The description of the preoperational monitoring program includes sampling frequency, 

48 sampling methods, and sampling locations and is in accordance with preoperational

49 monitoring guidance provided in Regulatory Guide 4.14 (NRC, 1980, Revision 1,

50 Section 1.1).
Site Characterization

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1 The monitoring results from the following types of samples have been obtained as 

2 described in Regulatory Guide 4.14 (NRC, 1980, Revision 1, Section 1.1): 

3

4 (a) Air Particulate and Radon Sampling. Preoperational air particulate and radon 

5 sampling results have been provided for a minimum of three locations at or near 

6 the site boundaries. If there are residences or occupiable structures within 16 km

7 [10 mi] of the site, sampling results from at least one location at or close to the 

8 nearest residence or occupiable structure is provided. Finally, sampling 

9 results from at least one control location remote from the site is provided. 

10 Preoperational air particulate samples have been collected as quarterly 

11 composites of weekly samples for 12 consecutive months and have been

12 analyzed for natural uranium, Th-230, Ra-226, and Pb-210. Preoperational 

13 radon samples were collected for 1 week during each month for 12 consecutive 

14 months and have been analyzed for Rn-222. Justification for alternative air 

15 particulate and radon sampling measurements has been provided,

16 when necessary.

17

18 (b) Groundwater Sampling. The applicant has provided data from groundwater 

19 samples collected quarterly from at least three sampling wells located 

20 hydrologically downgradient from the proposed surface impoundments

21 (e.g., tailings areas), at least three locations near other sides of the surface 

22 impoundments, and one well located hydrologically upgradient from the surface 

23 impoundments area that serves as background. In addition, the applicant has 

24 provided data from groundwater samples collected quarterly from each well 

25 within 2 km [1.2 mi] of the proposed tailings area. The samples have been

26 analyzed for dissolved and suspended natural uranium, Th-230, Ra-226, Po-210, 

27 and Pb-210. Quarterly groundwater sampling data from at least three wells 

28 located within the uppermost aquifer, at least three wells located hydrologically 

29 downgradient from the conventional or heap leach facility, and at least one well 

30 located hydrologically upgradient from the conventional and heap leach facility to 

31 serve as a background sample are provided. Groundwater sampling data from 

32 the aquifers below the uppermost aquifer are also provided, if there is a hydraulic 

33 connection between the uppermost aquifer and underlying aquifers and if the 

34 underlying aquifers are source of drinking water. The technical basis for 

35 choosing the sampling locations is described. Quarterly groundwater sampling 

36 data are also provided for each well within 2 km [1.2 mi] of the surface 

37 impoundments that is or could be used for drinking water, watering of 

38 livestock, or crop irrigation. Preoperational samples have been collected for

39 12 consecutive months (see SRP, Section 2.7.1). Justification for alternative 

40 groundwater sampling measurements has been provided, when necessary.

41

42 (c) Surface Water Sampling. If required, preoperational surface water sampling 

43 results are provided. Surface water samples from running and standing waters

44 are analyzed quarterly for natural uranium, Th-230, and Ra-226 and

45 semiannually for Pb-210 and Po-210. The locations include, but are not limited 

46 to, permanent and ephemeral creeks; river, ponds, lakes, and offsite 

47 impoundments that may be subject to direct surface drainage from potentially 

48 contaminated areas; surface waters or drainage systems crossing the site 

49 boundary; and surface waters that may be subject to drainage from potentially 

50 contaminated areas. These surface water samples are collected as a grab 

51 sample on a monthly and quarterly basis for surface impoundments and drainage 
Site Characterization

2-35

1 systems, respectively. Preoperational samples are collected for 12 consecutive 

2 months in accordance with Section 2.7.2 of this SRP. Justification for alternative 

3 surface water sampling measurements has been provided, when necessary.

4

5 (d) Vegetation, Food, and Fish Sampling. Preoperational vegetation, food, and fish 

6 sampling results are provided from (i) at least three times during the grazing 

7 season, three vegetation locations near the site in different sectors having the 

8 highest predicted airborne radionuclide concentration due to milling or heap 

9 leach operations; (ii) three food locations that include crops, livestock, at time of 

10 harvest or slaughter or removal of animals from grazing for each type of crop 

11 (including vegetable gardens) within 3 km [1.9 mi] of the site; and (iii) fish (if any) 

12 in each body of water that may be subject to seepage or surface drainage from 

13 potentially contaminated areas. Preoperational samples are collected for

14 12 consecutive months. Vegetation, food, and fish (edible portion) samples are

15 analyzed for natural uranium, Th-230, Ra-226, Pb-210, and Po-210. Justification 

16 is provided for any sampling data that are not provided. Justification for 

17 alternative vegetation, food, and fish sampling measurements has been

18 provided, when necessary.

19

20 (e) Soil Sampling. Preoperational soil sampling results have been provided for up to 

21 40 surface soil samples taken at a depth of 5 cm [2 in] collected at 300 m [110 ft] 

22 intervals to a distance of 1,500 m [5,000 ft] from the proposed locations for 

23 surface impoundments in 8 meteorological sectors and at 5 or more air 

24 particulate sampling stations. All soil samples have been analyzed for Ra-226. 

25 Soil samples collected at air particulate sampling locations and 10 percent of 

26 other soil samples (including at least 1 subsurface set) have been analyzed for 

27 natural uranium, Th-230, and Pb-210. Analysis of extra soil samples may be 

28 necessary for repeat samples collected at locations disturbed by site excavation, 

29 leveling, or contouring. Soil sampling results from areas disturbed by site 

30 excavation, leveling, or contouring also have been provided. Results from 

31 subsurface samples at a depth of 1 m [3.3 ft] are provided from the center of the 

32 proposed locations for surface impoundments and from distances of 750 m 

33 [2,500 ft] in each of the 4 compass directions. At least 12 consecutive months of 

34 soil sampling data have been provided prior to major site construction. Soil 

35 sampling is conducted at both a 5-cm [2-in] depth as described in Regulatory 

36 Guide 4.14 (NRC, 1980, Revision 1, Section 1.1.4) and at a depth of 15 cm [6 in] 

37 for background decommissioning data. Justification for alternative soil sampling 

38 measurements has been provided, when necessary.

39

40 (f) Sediment Sampling. Results from one set of sediment samples have been 

41 provided for each of the surface water locations described previously. Sediment 

42 samples have been analyzed for natural uranium, Th-230, Ra-226, and Pb-210. 

43 For surface water passing through the site, sediment sampling results, both 

44 upstream and downstream of the site, have been provided. Samples have been

45 collected following spring runoff and in late summer following an extended period 

46 of low flow, if possible. For each location, results from several sediment samples 

47 collected in a transverse across the body of water and composited for analysis 

48 have been provided. The applicant has committed to submit results of sediment 

49 sampling prior to beginning milling or heap leach operations. Justification for 

50 alternative sediment sampling measurements has been provided,

51 when necessary.
Site Characterization

2-36

1

2 (g) Direct Radiation Measurements. Prior to initiation of major construction, the 

3 applicant has committed to provide the results of gamma exposure rate (direct 

4 radiation) measurements. The number and location of the measurements are

5 consistent with Regulatory Guide 4.14 (NRC, 1980, Revision 1, Section 1.1.6). 

6 The applicant has determined the number and location of measurements based 

7 on the particular design of the mill or heap leach facility and support buildings, 

8 and waste management facilities. Measurement results also have been provided 

9 for the sites chosen for air particulate samples and for each location disturbed by 

10 site excavation, leveling, or contouring. Gamma exposure measurements have 

11 been made with passive integrating devices (such as thermoluminescent or 

12 optically stimulated-luminescence dosimeters), pressurized ionization chambers, 

13 or properly calibrated portable survey instruments. Direct radiation 

14 measurements using instruments have been only completed in dry weather and 

15 not during periods following rainfall or when the soil is abnormally wet. 

16 Justification for alternative direct radiation measurements has been provided,

17 when necessary.

18

19 (h) Radon Flux Measurements. Results from Rn-222 flux measurements have been

20 provided for three separate months during normal weather conditions in the 

21 spring through the fall when the ground is thawed. Results include 

22 measurements made at the center of the mill area and at locations 750 and 

23 1,500 m [2,500 and 5,000 ft] from the center in each of the 4 compass directions. 

24 Measurements taken when the ground is frozen, covered with ice or snow, or 

25 following periods of rain have not been included. When radon flux data 

26 are required, at least 12 consecutive months of radon flux data are provided prior 

27 to major site construction. Justification for alternative radon flux measurements 

28 has been provided, when necessary. 

29

30 2.8.1.4 Evaluation Findings 

31

32 If the staff determines that no license conditions are required for the description of the site 

33 preoperational radiological characteristics because the applicant or licensee provided adequate 

34 and complete information that fully addresses all relevant regulatory requirements, typically a 

35 single paragraph is sufficient for the evaluation findings section. Begin the section with the 

36 sentence: “NRC staff has completed its review of the description of the site preoperational

37 radiological characteristics at the conventional uranium mill or heap leach facility in accordance 

38 with Section 2.8.1.3 of the standard review plan.” Following this sentence, state what 

39 information the applicant provided in the application. As discussed in the introduction of 

40 this SRP, a bullet list or sentence format may be used to list what information the applicant 

41 has provided. 

42

43 After the description of the information the applicant provided, the following or a similar

44 statement can be added: “Based on the review conducted by NRC staff, the information 

45 provided in the application meets the applicable acceptance criteria of Section 2.8.1.3 of the 

46 standard review plan. Therefore, NRC staff concludes that the applicant’s description of 

47 the site preoperational radiological characteristics is acceptable and is in compliance with 

48 10 CFR Part 40, Appendix A, Criterion 7, which requires preoperational and operational 

49 monitoring programs.” As a concluding statement, indicate the reason why the applicant’s 

50 information is considered adequate and complete, and why or how that information complies 

51 with the identified regulatory requirements. 
Site Characterization

2-37

1 If license conditions are needed, then a more detailed discussion is typically required. Begin 

2 this section with the sentence: “NRC staff has completed its review of the description of the site 

3 preoperational radiological characteristics at the conventional uranium mill or heap leach facility 

4 in accordance with Section 2.8.1.3 of the standard review plan.” Following this sentence, state 

5 what information the applicant provided in the application, including identification of the 

6 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

7 bullet list or sentence format may be used to list what information the applicant has provided. 

8 Next, state why a license condition is needed, followed by the license condition or conditions. 

9

10 In a separate paragraph following the discussion of the required license condition(s), include the 

11 statement: “Based on the review conducted by NRC staff, the information provided in the 

12 application, supplemented by provisions of the license condition(s) discussed above, meets the 

13 applicable acceptance criteria of Section 2.8.1.3 of the standard review plan. Therefore, NRC 

14 staff concludes that the applicant’s description of the site preoperational radiological 

15 characteristics is acceptable and is in compliance with 10 CFR Part 40, Appendix A, Criterion 7, 

16 which requires preoperational and operational monitoring programs.” If not discussed in the 

17 preceding paragraph(s), include a statement or summation as to why or how the application and 

18 license condition(s) jointly comply with the identified regulatory requirements.

19

20 2.8.1.5 Reference

21

22 NRC. Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium 

23 Recovery Facilities.” Rev. 1. Washington, DC: U.S. Nuclear Regulatory Commission, Office of 

24 Nuclear Regulatory Research. 1980. 

25

26 2.8.2 Nonradiological Preoperational Monitoring

27

28 2.8.2.1 Areas of Review 

29

30 The staff should evaluate the applicant’s assessment of preoperational water quality 

31 of potentially affected surface water and groundwater resources within the proposed 

32 permit boundaries and adjacent properties. This information will provide the basis for 

33 evaluating potential effects of conventional mill or heap leach operations on the quality of 

34 local water resources. The staff should review a list of constituents to be sampled for 

35 preoperational concentrations.

36

37 2.8.2.2 Review Procedures

38

39 The staff should review the nonradiological preoperational monitoring program in accordance 

40 with 10 CFR Part 40, Appendix A, Criterion 7:

41

42 (1) Evaluate the applicant’s assessment of preoperational water quality. This information 

43 will provide the basis for evaluating potential effects of conventional mill or heap leach

44 operations on the quality of local water resources. 

45

46 (2) Review the list of constituents to be sampled, the groundwater and surface water 

47 sampling procedure, and method for excluding outliers (see Appendix E) in the samples. 

48 Review the applicant’s quality control procedure for groundwater and surface water 

49 sampling. Verify that a sufficient number of surface water and groundwater samples are 

50 collected to provide meaningful statistics, that samples are spaced in time sufficiently to 

51 capture temporal variations, and that the chemical constituents and water quality 
Site Characterization

2-38

1 parameters evaluated are sufficient to establish preoperational water quality, including

2 classes of use.

3

4 2.8.2.3 Acceptance Criteria

5

6 The applicant’s assessment of preoperational nonradiological characteristics is acceptable if it 

7 meets the following criteria:

8

9 (1) Preoperational groundwater quality has been determined for the uppermost aquifer. If 

10 there is any evidence that the uppermost aquifer may not be hydraulically isolated from 

11 underlying major aquifers, due to the absence of or through an ineffective underlying 

12 confinement, groundwater baseline parameters have been also provided for the 

13 underlying aquifers. Reasonably comprehensive chemical analyses of water 

14 samples from the uppermost aquifer have been made to determine preoperational 

15 baseline conditions.

16

17 (2) A sufficient number of preoperational surface and groundwater samples are collected to 

18 provide meaningful statistics so that samples are spaced in time sufficiently to capture 

19 temporal variations and that the chemical constituents and water quality parameters 

20 evaluated are sufficient to establish preoperational water quality, including classes of 

21 use. In particular:

22

23 (a) The applicant has provided a list of constituents sampled for preoperational

24 concentrations. Table 2.8.2-1 lists acceptable constituents for monitoring at 

25

Table 2.8.2-1. Typical Water Quality Indicators To Be Determined During Preoperational 

Data Collection

A. Trace and Minor Elements

Arsenic Iron Selenium

Barium Lead Silver

Boron Manganese Uranium

Cadmium Mercury Vanadium

Chromium Molybdenum Zinc

Copper Nickel

Fluoride Ra-226*

B. Common Constituents

Alkalinity Chloride Sodium

Bicarbonate Magnesium Sulfate

Calcium Nitrate

Carbonate Potassium

C. Physical Indicators

Specific Conductivity† Total Dissolved Solids‡

pH†

D. Radiological Parameters

Gross Alpha§ Gross Beta

*If site initial sampling indicates the presence of Th-232, then Ra-228 should be considered in the baseline sampling

or an alternative may be proposed.

†Field and laboratory determination.

‡Laboratory only.

§Excluding radon, radium, and uranium.

26
Site Characterization

2-39

1 conventional mill or heap leach facilities. Alternatively, the applicant may 

2 propose a list of constituents tailored to a particular location. If a detected 

3 constituent is excluded from the set of baseline parameters, the applicant 

4 provided the technical justification for their exclusion. For all constituents that are 

5 sampled, the applicant should maintain laboratory reports documenting the 

6 measurements. The applicant should show that water samples were collected by 

7 acceptable sampling procedures, such as ASTM D4448 (ASTM 

8 International, 2007).

9

10 (b) The applicant collected and analyzed at least four sets of samples, spaced 

11 sufficiently in time to indicate seasonal variability for each listed constituent for 

12 determining baseline water quality conditions. Some samples should be split and 

13 sent to different laboratories as part of a quality assurance program. Additional 

14 sampling to establish the natural cyclical fluctuations of the water quality is 

15 necessary if natural groundwater flow rates and recharge conditions vary 

16 considerably. The average water quality for each aquifer zone and the range of 

17 each indicator in the aquifer zone have been tabulated and evaluated. If regions

18 of distinct water quality characteristics are identified, then they are delineated 

19 and referenced on a topographic map.

20

21 (c) An outlier is a single nonrepeating value that lies far above or below the rest of 

22 the sample values for a single well. The outlier may represent a sampling, 

23 analytical, or other unknown source of error or an unidentified randomness in the 

24 data. Its inclusion within the sample could significantly change the baseline data, 

25 because the outlier is not typical of the bulk of the samples. Appendix E to this 

26 SRP provides guidance on proper statistical methods for dealing with outliers in 

27 the sample sets. All calculations, assumptions, and conclusions the applicant 

28 makes in evaluating outliers should be fully explained. If an extreme sample is 

29 determined to represent part of the natural variations, it should not be removed 

30 from the sample set.

31

32 (d) Preoperational water quality has been adequately determined for potentially 

33 affected surface water bodies within the proposed permit boundaries and 

34 adjacent properties. A number of preoperational surface water samples are

35 collected to provide meaningful statistics. Where perennial surface water 

36 sources are present, surface water quality measurements should be taken on a 

37 seasonal basis for a minimum of 1 year before implementation of conventional 

38 mill or heap leach operations. Surface water samples can be obtained by grab 

39 sampling and should be taken at the same location each time. 

40

41 2.8.2.4 Evaluation Findings 

42

43 If the staff determines that no license conditions are required for the description of the site 

44 preoperational nonradiological characteristics because the applicant or licensee provided 

45 adequate and complete information that fully addresses all relevant regulatory requirements, 

46 typically a single paragraph is sufficient for the evaluation findings section. Begin the section 

47 with the sentence: “NRC staff has completed its review of the description of the site 

48 nonradiological characteristics at the conventional uranium mill or heap leach facility in 

49 accordance with Section 2.8.2.3 of the standard review plan.” Following this sentence, state 

50 what information the applicant provided in the application. As discussed in the introduction of 

51
Site Characterization

2-40

1 this SRP, a bullet list or sentence format may be used to list what information the applicant 

2 has provided. 

3

4 After the description of the information the applicant provided, the following or a similar 

5 statement can be added: “Based on the review conducted by NRC staff, the information 

6 provided in the application meets the applicable acceptance criteria of Section 2.8.2.3 of the 

7 standard review plan. Therefore, NRC staff concludes that the applicant’s description of the 

8 site preoperational nonradiological characteristics is acceptable and is in compliance with 

9 10 CFR Part 40, Appendix A, Criterion 7, which requires preoperational and operational 

10 monitoring programs.” As a concluding statement, indicate the reason why the applicant’s 

11 information is considered adequate and complete, and why or how that information complies 

12 with the identified regulatory requirements.

13

14 If license conditions are needed, then a more detailed discussion is typically required. Begin 

15 this section with the sentence: “NRC staff has completed its review of the description of the site 

16 preoperational nonradiological characteristics at the conventional uranium mill or heap leach 

17 facility in accordance with Section 2.8.2.3 of the standard review plan.” Following this sentence, 

18 state what information the applicant provided in the application, including identification of the 

19 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

20 bullet list or sentence format may be used to list what information the applicant has provided. 

21 Next, state why a license condition is needed, followed by the license condition or conditions.

22

23 In a separate paragraph following the discussion of the required license condition(s), include the 

24 statement: “Based on the review conducted by NRC staff, the information provided in the 

25 application, supplemented by provisions of the license condition(s) discussed above, meets the 

26 applicable acceptance criteria of Section 2.8.2.3 of the standard review plan. Therefore, NRC 

27 staff concludes that the applicant’s the description of the site preoperational nonradiological 

28 characteristics is acceptable and is in compliance with 10 CFR Part 40, Appendix A, Criterion 7, 

29 which requires preoperational and operational monitoring programs.” If not discussed in the 

30 preceding paragraph(s), include a statement or summation as to why or how the application and 

31 license condition(s) jointly comply with the identified regulatory requirements.

32

33 2.8.2.5 Reference

34

35 ASTM International. “Standard Guide for Sampling Groundwater Monitoring Wells.” Guide 

36 D4448–01. West Conshohocken, Pennsylvania: ASTM International. 2007. 
3-1

1 3.0 DESCRIPTION AND DESIGN OF PROPOSED FACILITY

2

3 3.1 Conventional Uranium Mill Facilities

4

5 3.1.1 Areas of Review

6

7 The staff should review the description of the conventional uranium mill facilities provided in the 

8 application including: 

9

10 (1) A review of descriptions of the ore to be milled including, but not limited to, the estimated 

11 volume of ore-bearing rocks to be processed, the average grade of ore, and the mineral 

12 content of the ore.

13

14 (2) A review of descriptions of the proposed conventional uranium mill design and milling 

15 process. The applicant’s recovery plant is reviewed in Section 3.4 of this standard 

16 review plan (SRP).

17

18 (3) A review of the proposed operating plans and schedules that include timetables and 

19 sequences for conventional uranium mill operation.

20

21 3.1.2 Review Procedures

22

23 The staff should use the following procedures when reviewing the description of the 

24 conventional uranium mill facilities:

25

26 (1) Ensure that the applicant has identified the chemical composition of the ore, its 

27 estimated volume to be processed and average grade. This information should meet, in 

28 part, the requirements of 10 CFR 40.32(a).

29

30 (2) Determine that the applicant has adequately described the conventional uranium mill 

31 facilities. This description of the process and equipment is sufficiently detailed to 

32 characterize ore transport; ore crushing and grinding; leaching; and uranium extraction 

33 operations in the mill. This information should meet, in part, the requirements of,

34 10 CFR 40.31(h) and 10 CFR Part 40, Appendix A, Criterion 5H.

35

36 (3) Determine that proposed operating plans and schedules include timetables for 

37 conventional uranium mill operation. This information should meet, in part, the 

38 requirements of 10 CFR 40.31(h) and 10 CFR 40.41(c).

39

40 3.1.3 Acceptance Criteria

41 The description of the conventional uranium mill facilities is acceptable if it meets the 

42 following criteria: 

43

44 (1) The volume and source of ore-bearing rocks to be processed at the proposed facility 

45 has been described. The applicant has provided a detailed description of the ore to 

46 be processed, average grade, mineral content, and chemical form of its uranium 

47 content. If more than one type of ore is to be processed, each type of ore has been 

48 described separately.
Description and Design of Proposed Facility

3-2

1 (2) The applicant also has provided a detailed description of the proposed facilities and 

2 equipment for safe receiving, storing, and processing of ore-bearing source rocks at the 

3 proposed facility, including, but not limited to:

4

5 (a) A map or maps showing the facility’s location, including facilities for receiving, 

6 storing, and processing of ore;

7

8 (b) Diagrams showing the proposed (or existing) plant/facilities layout in 

9 adequate detail, including the license boundary and restricted area boundary;

10

11 (c) A flow diagram of the process or circuit, a material balance diagram, a 

12 description of any chemical recycle systems, and a water balance diagram for 

13 the entire system;

14

15 (d) A detailed description of each processing unit in the plant (e.g., crusher, grinder, 

16 uranium leaching circuit, solvent extraction/ion exchange circuit); and

17

18 (e) If materials are stockpiled, a description of the plan to minimize penetration of 

19 radionuclides into the soil below the stockpile.

20

21 (3) Proposed operating plans and schedules include timetables for conventional uranium 

22 mill operation. Water-balance calculations are provided to demonstrate that disposal 

23 facilities for mill tailings (surface impoundments) and process effluents (retention ponds, 

24 land application, and/or deep well injection) are adequate to dispose the proposed 

25 milling effluents during the license period.

26

27 3.1.4 Evaluation Findings 

28

29 If the staff determines that no license conditions are required for the description of the 

30 conventional uranium mill facilities because the applicant or licensee provided adequate and 

31 complete information that fully addresses all relevant regulatory requirements, typically a single 

32 paragraph is needed for the evaluation findings section. Begin the section with the sentence: 

33 “NRC staff has completed its review of the description of the conventional uranium mill

34 facilities in accordance with Section 3.1.3 of the standard review plan.” Following this 

35 sentence, state what information the applicant provided in the application. As discussed in 

36 the introduction of this SRP, a bullet or sentence format may be used to list what information

37 the applicant has provided. 

38

39 After the description of the information the applicant provided, the following or a similar 

40 statement can be added: “Based on the review conducted by NRC staff, the information 

41 provided in the application meets the applicable acceptance criteria of Section 3.1.3 of the SRP. 

42 Therefore, NRC staff concludes that the applicant’s description of the conventional uranium mill

43 facilities is acceptable and is in compliance with 10 CFR 40.31(h), which establishes 

44 requirements for license applications; 10 CFR 40.32(a), which requires that the application is for 

45 a purpose authorized by the Atomic Energy Act of 1954, as amended; 10 CFR 40.41(c), which 

46 requires the applicant to confine source or byproduct material to the location and purposes 

47 authorized in the license; and 10 CFR Part 40, Appendix A, Criterion 5H, which requires the 

48 applicant to minimize the penetration of radionuclides into underlying soil in a stockpile.” As a 

49 concluding statement, indicate the reason why the applicant’s information is considered 

50 adequate and complete, and why or how that information complies with the identified 

51 regulatory requirements.
Description and Design of Proposed Facility

3-3

1

2

3

4 If license conditions are needed, then a more detailed discussion is typically required. Begin 

5 this section with the sentence: “NRC staff has completed its review of the description of the 

6 conventional uranium mill facilities in accordance with Section 3.1.3 of the standard review 

7 plan.” Following this sentence, state what information the applicant provided in the application, 

8 including identification of the information that was omitted or inadequate. As discussed in the 

9 introduction of this SRP, a bullet or sentence format may be used to list what information the 

10 applicant has provided. Next, state why a license condition is needed, followed by the license 

11 condition or conditions. 

12

13 In a separate paragraph following the discussion of the required license condition(s), include the 

14 statement: “Based on the review conducted by NRC staff, the information provided in the 

15 application, supplemented by provisions of the license condition(s) discussed above, meets the 

16 applicable acceptance criteria of Section 3.1.3 of the standard review plan. Therefore, NRC 

17 staff concludes that the applicant’s description of the conventional uranium mill facilities is 

18 acceptable and is in compliance with 10 CFR 40.31(h), which establishes requirements for 

19 license applications; 10 CFR 40.32(a), which requires that the application is for a purpose 

20 authorized by the Atomic Energy Act of 1954, as amended; 10 CFR 40.41(c), which requires the 

21 applicant to confine source or byproduct material to the location and purposes authorized in the 

22 license; and 10 CFR Part 40, Appendix A, Criterion 5H, which requires the applicant to minimize 

23 the penetration of radionuclides into underlying soil in a stockpile.” If not discussed in the 

24 preceding paragraph(s), include a statement or summation as to why or how the application and 

25 license condition(s) jointly comply with the identified regulatory requirements.

26

27 3.1.5 References

28

29 None.

30

31 3.2 Heap Leach Facilities

32

33 3.2.1 Areas of Review

34

35 The staff should review the description of the heap leach facilities provided in the application. 

36 This review should include:

37

38 (1) A review of descriptions of the ore to be leached including, but not limited to, the 

39 estimated volume of ore-bearing rocks to be processed, the average grade of ore, the 

40 mineral content of the ore, and its suitability for leaching.

41

42 (2) A review of descriptions of the proposed heap leach facility design and leaching process. 

43 The review of applicant’s recovery plant is reviewed in Section 3.4 of this SRP.

44

45 (3) A review of the proposed operating plans and schedules that include timetables and 

46 sequences for heap leach facility operation.

47

48
Description and Design of Proposed Facility

3-4

1 3.2.2 Review Procedures

2

3 The staff should use the following procedures when reviewing the description of the heap 

4 leach facilities:

5

6 (1) Ensure that the applicant has identified the ore including its chemical composition, 

7 estimated volume to be processed, and average grade. This information should meet, in 

8 part, the requirements of 10 CFR 40.31(h).

9

10 (2) Verify the adequacy of the heap leach materials including the size distribution of the ore 

11 particles to be leached, strength and permeability of these particles, expected degree of 

12 packing in the heap, and any need for pretreatment of the ore. This information should 

13 meet, in part, the requirements of 10 CFR 40.31(h).

14

15 (3) Determine that the applicant has adequately described the leaching process and the 

16 heap leach facilities are sufficiently detailed to characterize the ore stockpile, if any; ore 

17 transport; ore crushing (size reduction) operations, and the heap leach process. This 

18 information should meet, in part, the requirements of 10 CFR 40.31(h), 10 CFR 40.41(c), 

19 and 10 CFR Part 40, Appendix A, Criteria 5E(2) and 5H.

20

21 (4) Determine that proposed operating plans and schedules include timetables for heap 

22 leaching operation, including disposal of liquid wastes. This information should meet, in 

23 part, the requirements of 10 CFR 40.31(h) and 10 CFR 40.41(c).

24

25 3.2.3 Acceptance Criteria

26

27 The description of the heap leaching facilities is acceptable if it meets the following criteria: 

28

29 (1) The applicant has identified the ore to be processed at the proposed heap leach facility 

30 and provided a detailed description of the ore including its chemical composition, source, 

31 average grade, mineral content, and chemical form of its uranium content. If more than 

32 one type of ore is to be processed, each type of ore has been described separately. 

33

34 (2) The described materials are appropriate for heap leaching, that is:

35

36 (a) The size distribution of ore particles will be commensurate with the specifications 

37 of the geomembrane to avoid puncture and associated leachate leak.

38

39 (b) The types of pretreatment needed for the materials have been described;

40 pretreatment of the ore can range from none (for “run of mine” ore particles) to 

41 crushing, grinding, and agglomeration in addition to any chemical pretreatments 

42 of the ore.

43

44 (c) The strength of the ore particles is adequate to resist the load imposed by the 

45 construction equipment to avoid significant compaction of the ore particles

46 resulting in a decrease of heap permeability, especially at the top of the heap.

47

48 (d) The expected degree of compaction is appropriate for sustaining an adequate 

49 leaching rate.

50
Description and Design of Proposed Facility

3-5

1 (e) The ore is available in porous and permeable host rock; and the permeability of 

2 the ore particles is adequate for the proposed leaching operations.

3

4 (f) The ore is relatively free of fines and/or clays that may restrict uniform 

5 percolation of the leaching solution.

6

7 (g) If materials are stockpiled, a plan exists to minimize penetration of radionuclides 

8 into the soil below the stockpile. 

9

10 (3) The application:

11

12 (a) Provides diagrams showing the proposed (or existing) facilities layout in 

13 adequate detail, including the license boundary and restricted area boundary;

14

15 (b) Includes a flow diagram of the process or circuit, a material balance diagram, a 

16 description of any chemical recycle systems, and a water balance diagram for 

17 the entire system;

18

19 (c) Includes a map or maps showing the facilities location, including facilities for 

20 receiving, storing, and processing ore-bearing source rocks; and

21

22 (d) Describes a process that maximizes solution recycling and water conservation.

23

24 The applicant also has provided a detailed description of proposed facilities and 

25 equipment for safe receiving, stockpiling, storing, and processing of ore-bearing source 

26 rocks at the proposed facility. The leach pad(s) have sufficient capacity to 

27 accommodate the entire quantity of ore to be leached.

28

29 (4) Proposed operating plans and schedules include timetables for heap leaching operation. 

30 Water-balance calculations are provided to demonstrate that disposal of leaching

31 process effluents (retention ponds, land application, and or deep well injection) is

32 adequate for disposal of the proposed milling effluents during the compliance period.

33

34 3.2.4 Evaluation Findings 

35

36 If the staff determines that no license conditions are required for the description of the heap 

37 leach facilities because the applicant or licensee provided adequate and complete information 

38 that fully addresses all relevant regulatory requirements, typically a single paragraph is 

39 needed for the evaluation findings section. Begin the section with the sentence: “NRC staff 

40 has completed its review of the description of the heap leach facilities in accordance with 

41 Section 3.2.3 of the standard review plan.” Following this sentence, state what information the 

42 applicant provided in the application. As discussed in the introduction of this SRP, a bullet or 

43 sentence format may be used to list what information the applicant has provided. 

44

45 After the description of the information the applicant provided, the following or a similar 

46 statement can be added: “Based on the review conducted by NRC staff, the information 

47 provided in the application meets the applicable acceptance criteria of Section 3.2.3 of the 

48 standard review plan. Therefore, NRC staff concludes that the applicant’s description of the 

49 heap leach facilities is acceptable and is in compliance with 10 CFR 40.31(h), which 

50 establishes requirements for license applications; 10 CFR 40.41(c), which requires the applicant 

51 to confine source or byproduct material to the location and purposes authorized in the license; 
Description and Design of Proposed Facility

3-6

1 10 CFR Part 40, Appendix A, Criterion 5E(2), which requires use of a process design that 

2 maximizes solution recycling and water conservation; and 10 CFR Part 40, Appendix A, 

3 Criterion 5H, which requires the applicant to minimize the penetration of radionuclides into 

4 underlying soil in a stockpile.” As a concluding statement, indicate the reason why the 

5 applicant’s information is considered adequate and complete, and why or how that information 

6 complies with the identified regulatory requirements.

7

8 If license conditions are needed, then a more detailed discussion is typically required. Begin 

9 this section with the sentence: “NRC staff has completed its review of the description of the 

10 heap leach facilities in accordance with Section 3.2.3 of the standard review plan.” Following 

11 this sentence, state what information the applicant provided in the application, including 

12 identification of the information that was omitted or inadequate. As discussed in the 

13 introduction of this SRP, a bullet or sentence format may be used to list what information

14 the applicant has provided. Next, state why a license condition is needed, followed by the 

15 license condition or conditions. 

16

17 In a separate paragraph following the discussion of the required license condition(s), include the 

18 statement: “Based on the review conducted by NRC staff, the information provided in the 

19 application, supplemented by provisions of the license condition(s) discussed above, meets the 

20 applicable acceptance criteria of Section 3.2.3 of the standard review plan. Therefore, NRC 

21 staff concludes that the applicant’s description of the heap leach facilities is acceptable and is in 

22 compliance with 10 CFR 40.31(h), which establishes requirements for license applications;

23 10 CFR 40.41(c), which requires the applicant to confine source or byproduct material to the 

24 location and purposes authorized in the license; 10 CFR Part 40, Appendix A, Criterion 5E(2), 

25 which requires use of a process design that maximizes solution recycling and water 

26 conservation; and 10 CFR Part 40, Appendix A, Criterion 5H, which requires the applicant to 

27 minimize the penetration of radionuclides into underlying soil in a stockpile.” If not discussed in 

28 the preceding paragraph(s), include a statement or summation as to why or how the application 

29 and license condition(s) jointly comply with the identified regulatory requirements.

30

31 3.2.5 References

32

33 None.

34

35 3.3 Design of Surface Impoundments

36

37 The following information is presented in a more detailed manner because of the nature of the 

38 regulations in 10 CFR Part 40, Appendix A.

39

40 3.3.1 Areas of Review

41

42 The staff should review the license application for the description, design, and proposed 

43 construction method of surface impoundments. The review of surface impoundments of a 

44 conventional uranium mill facility should include characteristics of the mill tailings, and locations 

45 and design of surface impoundments under static and earthquake loads in reference to slope 

46 stability, potential liquefaction, seepage, and consolidation/settlement. In addition, effects of soil 

47 and/or synthetic liners, leak detection systems, and design and construction of the erosion 

48 protection cover should be reviewed. The review should include effects of uncertainties of 

49 shape of the slope, applied load, and material properties including any spatial variations of the 

50 parameters to ensure that they have been adequately characterized. 
Description and Design of Proposed Facility

3-7

1 The review should include location of the leach pad(s) including surrounding topography, 

2 characteristics of leach materials, and type of leach pads and associated design. The staff 

3 should assess the leach pad characteristics, foundation design, liner system(s), and solution 

4 (leachate) collection and leak detection system(s). In addition, the staff should review the 

5 design of leach solution and barren solution ponds, and monitoring and inspection of the heaps. 

6 The review should also include the method of pad loading; static and dynamic loads that may be 

7 imposed on the liner system and also on the geomembrane, if used; and design of collection 

8 pipes. In addition, the stability of the heap leach pad under seismic conditions including any 

9 potential liquefaction under seismic loads should be reviewed. This review should be 

10 coordinated with the review of geological/geotechnical, stratigraphical, seismological, and 

11 hydrological information as described in this SRP.

12

13 Surface impoundments of a conventional uranium mill and a heap leach facility have many 

14 similar characteristics, although each has a few unique features. Consequently, the staff has 

15 developed this SRP section for reviewing the design, construction, and inspection/maintenance 

16 of an existing or a new conventional uranium mill facility or heap leaching facility in the license 

17 application. Review procedure(s) unique to a particular type of facility have been clearly 

18 identified in this section.

19

20 3.3.2 Review Procedures

21

22 The staff should use the following procedures to review the design of surface impoundments.

23

24 Site Selection

25

26 (1) Verify that the technical basis for selecting the location of the surface impoundments is 

27 adequate, as discussed in Section 2 of this SRP. This information should meet, in part, 

28 the requirements of 10 CFR Part 40, Appendix A, Criteria 1, 4(a), and 4(b).

29

30 Site-Specific Information

31

32 (2) Verify that the geological and geotechnical data obtained from site investigations are 

33 appropriate and conservative for the assumptions and analyses presented in the license 

34 application. Ensure that the spatial variability of the geotechnical parameters of the 

35 underlying soil and geologic formations (e.g., soil type, soil density, soil layer thickness, 

36 soil strength properties, continuity of layers, depth to groundwater) have been 

37 characterized adequately and incorporated into the design analysis. This information 

38 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 1 

39 and 5G(2).

40

41 (3) For an existing facility, verify that the applicant has provided adequate information on 

42 sand and slime tailings. Ensure that this information includes the sand and slime tailings 

43 characteristics, spatial extent, and spatial variation of depth and thickness of each layer. 

44 This information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

45 Criteria 1 and 5G(2).

46

47 Design of Surface Impoundments

48

49 (4) Verify that the design description of the surface impoundment is sufficiently detailed. 

50 This information should meet, in part, the requirements of 10 CFR 40.31(h) and 

51 10 CFR Part 40, Appendix A, Criteria 1 and 4(b)–(d).
Description and Design of Proposed Facility

3-8

1 (5) Verify that the capacity of the surface impoundment would be sufficient to dispose all 

2 tailings and other byproduct material generated through the lifecycle of the facility. This 

3 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

4 Criteria 1 and 6A(3).

5

6 (6) Verify that the tailings will be disposed below grade. If full below-grade disposal is not 

7 practical or environmentally sound, ensure that the tailings retention system would be 

8 appropriately located and sized so that the slope angles of the embankment and final 

9 cover would be relatively flat after final stabilization for long-term stability and 

10 minimum erosion potential. This information should meet, in part, the requirements 

11 of 10 CFR Part 40, Appendix A, Criteria 3 and 4(c). 

12

13 (7) Ensure that the applicant has provided the technical justification for final slopes of the

14 surface impoundments steeper than five horizontal (5h) to one vertical (1v) unit. This 

15 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

16 Criteria 1 and 4(c).

17

18 (8) Verify that freeboard in surface impoundments is sufficient to prevent any overtopping at 

19 all times. This information should meet, in part, the requirements of 10 CFR Part 40, 

20 Appendix A, Criterion 5A(4).

21

22 (9) Verify that adequate protection has been provided for embankment and cover slope 

23 stability against wind and water erosion, weathering, and ice damage. This information 

24 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 1, 3, 

25 and 4(d). 

26

27 Foundation Design

28

29 (10) Ensure that the foundation of the surface impoundment is able to withstand the 

30 anticipated static and dynamic/seismic loads, including the differential 

31 stress/deformation, so that the integrity and function of the liner system and any 

32 under-pad leak detection system are maintained. This information should meet, in part, 

33 the requirements of 10 CFR Part 40, Appendix A, Criteria 5A(2) and 5G(2).

34

35 (11) Verify that the top of the foundation exhibits a low permeability. This information should 

36 meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 5A(2) and 5G(2).

37

38 Liner Design

39

40 (12) Verify that the design of the liner system for the surface impoundment has been 

41 described. Also, verify that materials of appropriate quality are available in sufficient 

42 quantity. Ensure that the technical basis for selection of the liner system has been

43 provided, the selected liner system has been demonstrated to be physically and 

44 chemically inert to the waste materials in the surface impoundment, and the selected 

45 liner system has sufficient thickness and strength to prevent failure from hydrologic 

46 pressure gradient, climatic conditions, stress of installation (i.e., construction equipment 

47 and materials), and stress of daily operations (i.e., initial loading). This information 

48 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 1 

49 and 5A(2).

50
Description and Design of Proposed Facility

3-9

1 (13) Verify that a liner has been designed, constructed, and will be installed to prevent 

2 leakage from surface impoundments to the surrounding environment. Also, verify that 

3 the applicant has established an allowable leakage rate for the liner and provided 

4 adequate technical justification. Ensure that the liner system has sufficient strength and 

5 thickness to prevent failure due to pressure gradient, settlement, compression, or uplift

6 when placed upon a foundation. Verify that adequate protective measures to prevent 

7 any damage or puncture of the liner system have been described. This information 

8 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 1, 

9 and 5A(2).

10

11 (14) Ensure that a leak detection system will be installed immediately below the liner. Also, 

12 ensure that the design of the leak detection system will be effective in detecting a leak 

13 and identifying its location for repair. This information should meet, in part, the 

14 requirements of 10 CFR Part 40, Appendix A, Criteria 1 and 5E(1).

15

16 Cover Design 

17

18 (15) Ensure that the applicant has described the proposed cover to be placed over the 

19 surface impoundment including any long-term erosion-protection features. Verify that 

20 information also includes materials to be used for construction and associated borrow 

21 areas. If a geomembrane is proposed as a part of the cover, ensure that description of 

22 the geomembrane and method of construction are provided. This information should 

23 meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 1, 4(d), 6(1), 

24 and 6(5).

25

26 Leachate Storage Pond in Heap Leach Facility

27

28 (16) Ensure that the applicant has provided an adequate description of the leachate storage 

29 pond, including the capacity, liner materials, stability, and description of the pond, 

30 especially the side slopes. Verify that the liner characteristics meet the requirements 

31 specified in review procedures 12 through 14 of this section of the SRP. This 

32 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

33 Criteria 5A(1), 5A(2), 5A(3), and 5E(1). 

34

35 Barren Solution Pond in a Heap Leach Facility

36

37 (17) Verify that the applicant has provided an adequate description of the barren solution 

38 pond, including the capacity, liner materials, stability, and description of the pond, 

39 especially the side slopes. Verify that the liner characteristics meet the requirements 

40 specified in review procedures 12 through 14 of this section of the SRP. This 

41 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

42 Criteria 5A(1), 5A(2), 5A(3), and 5E(1).

43

44 Other Types of Ponds

45

46 (18) Verify that other types of ponds (e.g., evaporation ponds) in a conventional uranium mill 

47 or a heap leach facility are designed appropriately for effective containment, including 

48 the capacity, liner materials, stability, and description of the pond, especially the side 

49 slopes. Verify that the liner characteristics meet the requirements specified in review 

50 procedures 12–14 of this section of the SRP. This information should meet, in part, the 

51 requirements of 10 CFR Part 40, Appendix A, Criteria 5A(1), 5A(2), 5A(3), and 5E(1).
Description and Design of Proposed Facility

3-10

1 Dewatering of Tailings/Leachate Collection System

2

3 (19) Verify that a system to dewater the tailings at the bottom of the impoundment to lower 

4 the phreatic surface and reduce the driving seepage head has been described. This 

5 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A,

6 Criterion 5E(3).

7

8 (20) Ensure that the applicant has provided an adequate description of the leachate 

9 collection system to be used in the surface impoundment. Review the design rate of 

10 leachate flow, construction materials, method of construction, design of leachate pond, 

11 and effectiveness of the heap leach pad design. This information should meet, in part, 

12 the requirements of 10 CFR Part 40, Appendix A, Criterion 5E(3).

13

14 (21) Ensure that the applicant has demonstrated that drains of the dewatering system of 

15 the surface impoundment and/or the leachate collection system will remain free 

16 running and adequately sized. This information should meet, in part, the requirements 

17 of 10 CFR Part 40, Appendix A, Criterion 5E(3).

18

19 Slope Stability

20

21 (22) Ensure that the applicant has provided sufficient design details on the surface 

22 impoundment or heap leach facility to conduct the stability analyses. This information 

23 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criterion 5A(5).

24

25 (23) Verify that the applicant has provided a basis for selecting specific locations of soil/rock 

26 profiles and cross sections of the surface impoundment at a sufficient number of 

27 locations including values of relevant parameters. This information should meet, in part, 

28 the requirements of 10 CFR Part 40, Appendix A, Criterion 5A(5).

29

30 (24) Verify that the applicant has assessed the stability of a surface impoundment, 

31 deterministically or probabilistically, using an acceptable method. Verify that the 

32 analysis presented used the most probable values or appropriate range of values for the

33 parameters involved, if deterministic approach is used. Alternatively, assess the method 

34 used by the applicant to quantify the probability of unsatisfactory performance, Pup, or 

35 reliability of an embankment (1 - Pup). This information should meet, in part, the 

36 requirements of 10 CFR Part 40, Appendix A, Criterion 5A(5).

37

38 (25) Verify that appropriate material properties of the surface impoundment have been used 

39 in stability assessment. Ensure that the boundaries and material properties of the 

40 surface impoundment used in stability assessment accounted for the associated 

41 uncertainties. Verify that the uncertainties associated with strength and loading 

42 parameters are appropriately represented by the probability distributions selected if a 

43 probabilistic approach is used. This information should meet, in part, the requirements 

44 of 10 CFR Part 40, Appendix A, Criterion 5A(5).

45

46 (26) Verify that the maximum credible earthquake and the associated seismic load have been 

47 considered in the stability analysis of the surface impoundment and that they will not be 

48 located near a capable (active) fault. This information should meet, in part, the 

49 requirements of 10 CFR Part 40, Appendix A, Criteria 4(e) and 5A(5).

50
Description and Design of Proposed Facility

3-11

1 (27) Ensure that reasonable ranges of material parameters have been considered in the 

2 analysis if the estimated factor of safety or the reliability index of the surface 

3 impoundments is low and that effects of other factors, such as flooding conditions, pore 

4 pressure effects, possible material erosion, and seismic effects, are conservatively 

5 considered. This information should meet, in part, the requirements of 10 CFR Part 40, 

6 Appendix A, Criterion 5A(5).

7

8 (28) Verify that the applicant has designed stable surface impoundments that have been 

9 demonstrated to be able to withstand anticipated static and dynamic loads. This 

10 information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

11 Criterion 5A(5).

12

13 (29) Determine whether a surface impoundment that would continue to hold process 

14 effluents after the cessation of operations meets the definition of a dam as provided in 

15 Federal Emergency Management (2004). If so, determine whether or not it has been 

16 classified as a structure with a low- or high-hazard potential. If the hazard potential is 

17 high, evaluate the emergency action plan for the facility. This information should meet, 

18 in part, the requirements of the Federal Dam Safety Program of U.S. Federal Emergency 

19 Management Agency.

20

21 Liquefaction

22

23 (30) Review the analysis of liquefaction potential of the surface impoundments by reviewing

24 the results of geotechnical investigations and in-situ tests, such as standard penetration, 

25 cone penetration, piezocone, density, and strength tests, as well as boring logs, 

26 laboratory classification test data, water table measurements, locations of perched water 

27 zones, and soil profiles, to determine whether any of the site soils or the tailings could be 

28 susceptible to liquefaction. Ensure that site exploration programs, the laboratory test 

29 program, and analyses are adequate to assess whether soils are susceptible to 

30 liquefaction beneath the site or in the surface impoundments. This information should 

31 meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criterion 5A(5).

32

33 (31) Ensure that the liquefaction potential of the surface impoundment have been adequately 

34 characterized using appropriate method(s). Determine that liquefaction has been 

35 mitigated or eliminated where the potential exists. Verify that minor or local liquefaction 

36 potentials are included in settlement analyses. This information should meet, in part, the 

37 requirements of 10 CFR Part 40, Appendix A, Criteria 5A(5), and 5G(2).

38

39 Settlement

40

41 (32) Ensure that the applicant has provided a settlement measurement and monitoring plan 

42 for the surface impoundment. This information should meet, in part, the requirements of 

43 10 CFR Part 40, Appendix A, Criteria 5A(4), 5A(5), and 6(1).

44

45 (33) Verify that the method used to assess settlement is appropriate for estimating both 

46 instantaneous settlement and secondary settlement due to pore pressure dissipation 

47 and long-term creep. Verify that an analysis of immediate settlement of tailings 

48 surfaces has been provided. This information should meet, in part, the requirements of 

49 10 CFR Part 40, Appendix A, Criteria 5A(4), 5A(5), and 6(1).

50
Description and Design of Proposed Facility

3-12

1 (34) Verify that the magnitude of total and differential settlements has been shown to be 

2 within limits that will not induce cracking of the dikes (embankments), if used to form the 

3 surface impoundment, leading to instability. In addition, verify that the expected 

4 settlement will not reduce freeboard of the surface impoundment. This information 

5 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criteria 5A(4) 

6 and 5A(5).

7

8 Construction

9

10 (35) Verify that the configuration of the proposed surface impoundment has enough capacity 

11 to contain all tailings and other contaminated materials that could be generated during 

12 operations. This information should meet, in part, the requirements of 10 CFR Part 40, 

13 Appendix A, Criterion 5A(4).

14

15 (36) Ensure that the applicant has provided a detailed plan and schedule for constructing the 

16 surface impoundment. Also, ensure that the applicant has described the construction 

17 sequence in sufficient detail. This information should meet, in part, the requirements of 

18 10 CFR Part 40, Appendix A, Criteria 1, 4(c), 5A(2), 5A(4), and 5A(5).

19

20 (37) Verify that the applicant demonstrates that the moisture content of borrow materials will 

21 be sufficient to allow the required degree of compaction. In addition, ensure that the 

22 applicant has indicated the duration and season for completing the construction 

23 activities. Additionally, verify that the applicant describes how borrow materials will be 

24 compacted with appropriate compaction equipment. Ensure that material placement and 

25 compaction procedures, moisture content, placement density and permeability, and 

26 schedule will meet the design specifications. Additionally, ensure that the proposed 

27 quality control program for construction of the surface impoundments is adequate to 

28 ensure adherence to the design specifications. This should include measures to protect 

29 the liner system during construction and initial loading. This information should meet, in 

30 part, the requirements of 10 CFR Part 40, Appendix A, Criterion 5A(2).

31

32 (38) Verify that the applicant demonstrates that proper subgrade preparation will be 

33 conducted for installing the liner system. If necessary, ensure that the applicant 

34 demonstrates that moisture of the subgrade soil will be conditioned to prevent drying 

35 before the liner is placed. This information should meet, in part, the requirements of

36 10 CFR Part 40, Appendix A, Criterion 5A(2).

37

38 (39) Verify that the applicant has demonstrated that the seams of the synthetic liner system, if 

39 used, will be placed and tested for integrity as per manufacturer’s recommendations. 

40 This information should meet, in part, the requirements of 10 CFR Part 40, Appendix A,

41 Criterion 5A(2).

42

43 Inspection and Monitoring

44

45 (40) Ensure that an inspection program for the surface impoundment using a qualified 

46 engineer or scientist has been described and that the applicant commits to 

47 documenting these inspections. This information should meet, in part, the requirements 

48 of 10 CFR Part 40, Appendix A, Criterion 8A.

49

50 (41) Verify that, after operational activities begin, the applicant commits to performing 

51 inspections at regular intervals to check the conditions of the surface impoundment and 
Description and Design of Proposed Facility

3-13

1 associated facilities and to evaluate the operational adequacy. Ensure that the applicant 

2 has adequately described the instrumentation to be used for inspection. Ensure that the 

3 proposed frequency of inspections of each element of the surface impoundment accounts 

4 for the size, nature of the foundation, and consequences of failure. Ensure that the 

5 inspection plan dictates that the surface impoundment will be inspected after a major 

6 natural event (e.g., a major earthquake with a nearby epicenter or a major rainfall event). 

7 This information should meet, in part, the requirements of 10 CFR 40.27(b)(2) and 

8 10 CFR Part 40, Appendix A, Criteria 1 and 8A.

9

10 3.3.3 Acceptance Criteria

11

12 The design of surface impoundments is acceptable if they meet the following criteria.

13

14 Site Selection

15

16 (1) The technical basis for selecting suitable locations for surface impoundments, as 

17 discussed in Section 2 of this SRP, has been provided. 

18

19 Site-Specific Information

20

21 (2) Data from site investigations were used to describe the surface impoundments.

22

23 (a) Data used are site-specific, appropriate, and conservative.

24

25 (b) The geotechnical parameters of the subgrade materials (e.g., soil 

26 cohesion and friction, thickness and continuity of the layers) have been 

27 adequately characterized.

28

29 (3) The applicant has provided information on sand and slime tailings for an existing surface 

30 impoundment in the reclamation plan, which includes, at a minimum:

31

32 (a) Characteristics of sand and slime tailings at the facility; and

33

34 (b) Variation of depth and thickness of sand and slime layers spatially and also 

35 vertically in the surface impoundment, including the basis of this information.

36

37 Design of Surface Impoundments

38

39 (4) The applicant has provided sufficient design description of the surface impoundment. 

40 The description includes, at a minimum, the following, as applicable:

41

42 (a) Dimensions of the surface impoundment and/or any retaining dike (embankment) 

43 including outside and inside slope angles;

44

45 (b) For an existing surface impoundment, history of operation and quantity, 

46 characteristics, and method of placement of the tailings;

47

48 (c) For a proposed surface impoundment, quantity and expected characteristics of 

49 the tailings and any other contaminated materials, proposed rate and method of 

50 placement of tailings, any dike or embankment to act as a retaining structure, 

51 and anticipated operating life of the impoundment; and
Description and Design of Proposed Facility

3-14

1 (d) For a heap leach facility: 

2

3 (i) The proposed heap leaching method and its appropriateness for the site 

4 considering topography and type and quantity of ore. 

5

6 (ii) The heap leaching method selected is appropriate for the local 

7 topography, space availability, and expected production capacity. Heap 

8 and pad dimensions have been provided. The area of the pad base, 

9 number of cells to be constructed and method(s) of their construction, 

10 height of each lift of ore placed for leaching, final pad height, equipment 

11 to be used and sequence of stacking ore, and slope of the heap have 

12 been adequately described. In addition, the number of lifts planned to 

13 reach the final pad height has been specified.

14

15 (iii) The applicant has provided the selected outside slope angle of the heap. 

16 If the slope is steep (e.g., the slope angle is close to the angle of repose 

17 of the materials), the design of the heap calls for benching or multiple lifts 

18 to reduce the overall slope angle for resisting instability or excessive 

19 erosion (Strachan and Dorey, 1988). Stability of the heap will be 

20 evaluated under acceptance criterion 28 of this section of the SRP.

21

22 (iv) The anticipated operating life of each new lift and the pad has been 

23 provided. Characteristics of the leaching solution and method and rate of 

24 application of the leaching solution have been provided.

25

26 (v) The method of application of the leaching solution to the heap has been 

27 provided (Muhtadi, 1988).

28

29 (vi) The description of other components of the facility, such as surface 

30 impoundments, has been provided.

31

32 (5) The surface impoundment has sufficient capacity to accommodate all leached materials 

33 and any other byproduct material throughout the complete lifecycle of the facility, 

34 considering uncertainties in volume estimates.

35

36 (6) Disposal of tailings in a below-grade facility is the preferred option. If the applicant 

37 demonstrates that above-grade disposal is necessary for environmental or practical 

38 reasons, the applicant has demonstrated that the retention system would be 

39 appropriately located and sized so that the steepness of the final stabilization slopes 

40 are minimized. 

41

42 (7) If above-grade disposal is proposed, the steepness of the final surfaces of the surface 

43 impoundments is a minimum of five horizontal units (5h) to one vertical unit (1v). If the 

44 proposed slopes are steeper than 5h:1v, a technical justification is provided describing 

45 why a 5h:1v or flatter slope would be impractical. If necessary, the applicant has 

46 demonstrated that given the site-specific conditions, a steeper slope is needed and that 

47 the use of a steeper slope provides an equivalent level of stabilization and containment 

48 for protection of public health, safety, and the environment. Stability of the slopes will be 

49 evaluated under acceptance criterion 28 of this section of the SRP. In addition, 
Description and Design of Proposed Facility

3-15

1 compensating features have been incorporated in the slope design to assure long-term 

2 stability when slopes are steeper than 5h:1v.

3

4 (8) The surface impoundments are designed, constructed, maintained, and operated to 

5 prevent overtopping resulting from (i) normal or abnormal operations, overfilling, wind 

6 and wave actions, rainfall, or run-on; (ii) malfunctions of level controllers, alarms, or 

7 other equipment; and (iii) human error. If dikes are used to form the surface 

8 impoundment, the dikes are designed, constructed, and maintained with sufficient 

9 structural integrity to prevent massive failure of the dikes.

10

11 (9) At the surface impoundment, adequate protection has been provided to prevent wind 

12 and water erosion, weathering, ice damage, and piping in the retention embankment or 

13 the foundation.

14

15 Foundation Design

16

17 (10) The applicant has demonstrated that the foundation of the surface impoundment is able 

18 to withstand the anticipated static and dynamic/seismic loads using laboratory and/or 

19 field experimental results. The foundation is able to withstand the differential 

20 stress/deformation so that the integrity and function of the liner system and any 

21 under-pad leak detection system can be maintained.

22

23 (11) The top part of the foundation acts as a barrier to vertical fluid flow and, consequently, 

24 has a very low hydraulic conductivity. JBR Environmental Consultants, Inc. (1998) 

25 suggests that the top 0.3 m [12 in] of the foundation of a heap leach pad have a 

hydraulic conductivity of 1 × 10–6 cm/s [3 × 10–6 26 in/s] or less. Adequate technical 

27 justification has been provided for other hydraulic conductivity values for the top part of 

28 the foundation.

29

30 Liner Design

31

32 (12) The applicant describes the design of the liner system for the surface impoundment 

33 including leachate storage ponds. At a minimum, design details, drawings, and pertinent 

34 analyses have been provided. Expected construction methods, testing criteria, and 

35 quality assurance programs have been presented. In addition, the applicant has 

36 provided the source(s) of the materials to be used in constructing the liner. These 

37 materials are available in acceptable quality and in sufficient quantities to construct the 

38 liner. The soil to be used in constructing the liner and liner bed is characterized to define 

39 the mechanical and hydraulic properties.

40

41 The applicant provides justification for the selection of the liner system including the type 

42 and thickness of the geomembrane to be used, if applicable. The liner will be 

43 constructed of materials that have appropriate chemical properties for use in the facility. 

44 Compatibility with waste, leachate, and any other liquids used in operation were tested 

45 using appropriate test parameters (e.g., temperature range) and design requirements 

46 (e.g., ASTM International, 2009a,b, 2008a, 2007a). 

47

48 The applicant has submitted test results on the longevity of the proposed liner system, 

49 and the test results show conclusively that the liner will not deteriorate when subjected to 

50 the waste products and expected atmospheric and temperature conditions at the site. If 

51 a clay liner system has been selected, the potential increase in hydraulic conductivity 
Description and Design of Proposed Facility

3-16

1 due to development of cracks from excessive differential settlement, drying 

2 (desiccation), and alteration of liner permeability due to geochemical reactions have 

3 been considered (Van Zyl, et al., 1988). This increase in hydraulic conductivity 

4 reduces the effectiveness of earthen liner systems, and the increase has been 

5 appropriately considered. 

6

7 The applicant has provided the thickness of the geomembrane liner, if applicable, and 

8 demonstrated that it is adequate for the expected loads to be encountered. The 

9 applicant has specified the engineering properties of the geomembrane liner to be used 

10 in the project, if applicable. These properties include resistance to rock puncture, 

11 adequate elongation capacity to withstand settlement under heap loads (seam tests for 

12 strength and water tightness), adequate frictional strength with ore particles and 

13 under-liner materials for slope stability assessment, and resistance to degradation due to 

14 long-term exposure to the climactic conditions expected (including resistance to 

15 ultraviolet light) (Lupo and Morrison, 2007; Gilbert, et al., 1996; Deatherage, et al., 

16 1988). The geomembrane liner proposed to be used in the heap leach pad is able to 

17 withstand the loads imposed by the dynamic construction traffic and final static loads, 

18 including any irregularities of the foundation. Additionally, the applicant has 

19 demonstrated that the liner has adequate puncture-resistance capabilities based on liner 

20 puncture performance tests (Thiel and Smith, 2004). The applicant has considered 

21 protective measures such as the use of low ground pressure equipment, visual 

22 inspection of first layer of material placed, construction techniques to minimize stresses 

23 on the liner system, or inclusion of sacrificial geosynthetics. 

24

25 (13) The proposed design of the liner system has considered subgrade materials, the type of 

26 liner system, liner system protection, and detection of leaks. Additionally, it addresses 

27 the anticipated installation techniques and operating practices. Proposed construction 

28 procedures include provisions for modification of the moisture condition of subgrade soil. 

29 The subgrade has been demonstrated to be competent to take the construction traffic so 

30 that anticipated settlement of the subgrade will not damage the liner system. The 

31 subgrade has been found to be sufficient to prevent failure of the liner because of 

32 settlement, compression, or uplift. The applicant has also agreed to install liners to 

33 cover all surrounding earth that is likely to be in contact with the wastes or leachate. 

34 Proper preparation of the subgrade and slopes of an impoundment is important to the 

35 success of the surface impoundments. The strength of the liner is heavily dependent 

36 on the stability of the slopes. The applicant has agreed to treat the subgrade with a 

37 soil sterilant. The applicant has established an allowable leakage rate of the liner taking 

38 into consideration the expected defect rates in the synthetic liner, if used; hydraulic 

39 shear strength of the liner system; and the flow rates within the detection layer. If the 

40 observed leakage rate is more than the allowable leakage rate, remedial actions would 

41 be taken (NRC, 2008).

42

43 The applicant has provided adequate technical justification for the materials including 

44 their size distribution, hydraulic conductivity, and moisture content to be used in 

45 constructing the bed for placing the geomembrane. The bed under the geomembrane 

46 liner should be composed of fine particles to minimize the risk of rock particles 

47 puncturing the geomembrane. An adequate technical justification has been provided for 

48 maximum particle size, moisture content, and hydraulic conductivity of the bedding soil.

49

50 The applicant has provided adequate information on the characteristics of the over-liner 

51 or geomembrane cover fill layer. Information includes the size distribution of the 
Description and Design of Proposed Facility

3-17

1 materials to be used, layer thickness, and permeability in addition to the characteristics 

2 of the geomembrane. The geomembrane is chemically inert to the chemicals to be used 

3 for leaching.

4

5 The thickness and hydraulic conductivity of the over-liner or geomembrane cover are 

6 adequate to protect the liner or geomembrane. JBR Environmental Consultants, Inc. 

7 (1998) suggests that the over-liner or cover of the geomembrane should be thicker than 

0.6 m [2 ft] with the maximum hydraulic conductivity of 1 × 10–7 cm/s [3 × 10–7 8 in/s]. 

9 Sufficient technical justification has been provided if other design parameters for the 

10 over-liner or the geomembrane cover are proposed.

11

12 The size distribution of particles in the over-liner or geomembrane cover fill layer is 

13 commensurate with the specifications of the geomembrane, if applicable. Hydraulic 

14 conductivity of the over-liner or geomembrane cover fill layer is higher than the overlying 

15 ore lifts to maintain low hydraulic heads on the liner system for quick recovery of the 

16 leachate solution.

17

18 A quality control program has been established for the following factors when developing 

19 surface impoundments: (i) clearing, grubbing, and stripping; (ii) excavation and backfill; 

20 (iii) rolling; (iv) compaction and moisture control; (v) finishing; (vi) subgrade sterilization; 

21 and (vii) liner subdrainage and gas venting. The licensee has committed to perform 

22 inspections of the liner, liner slopes, and other earthwork features. Any damage or 

23 defects that could result in leakage will be immediately reported to the NRC staff. 

24 Appropriate repairs will be implemented as soon as possible.

25

26 The applicant has agreed to perform tests on seams of synthetic liners along the entire 

27 length of the seam. Representative sampling may be used for factory seams using 

28 testing methods recommended by the liner manufacturer. Compatibility tests that 

29 document the compatibility of the field seam material with the waste products and 

30 expected weather conditions will be submitted for staff review and approval. If it is 

31 necessary to repair the liner, representatives of the liner manufacturer will be called on 

32 to supervise the repairs.

33

34 For clay liners, at a minimum, the licensee has committed to conduct tests such as 

35 falling head permeameter tests performed on columns of liner material obtained during 

36 and after liner installation. These tests will determine the expected reaction of the 

37 impoundment liner to any combination of solutions or atmospheric conditions before the 

38 liner is exposed to them. 

39

40 (14) In ensuring structural integrity, the applicant does not assume that the liner system will 

41 function without leakage during the active life of the surface impoundment. A leak 

42 detection system is included at all surface impoundments using natural or synthetic 

43 liners. The applicant has provided sufficient information on the under-pad leak detection 

44 and collection system. The leak detection system is designed to (i) detect accidental 

45 leaks from the impoundment, (ii) identify the location of the leak so that liner repair can 

46 be implemented immediately, and (iii) isolate the leakage and control it. The applicant 

47 has demonstrated the following:

48

49 (a) Soil or fine particles will not migrate to the leak detection system.

50
Description and Design of Proposed Facility

3-18

1 (b) Aggregate material to be used as a seepage detection medium has a high 

2 hydraulic conductivity. JBR Environmental Consultants, Inc. (1998) suggests a 

3 hydraulic conductivity of the seepage detection medium should not be less than 

1 × 10–2 cm/s [3 × 10–2 4 in/s] for the aggregate material to be effective as a 

5 seepage detection medium. Sufficient technical justification has been provided if 

6 other values of hydraulic conductivity are proposed.

7

8 The surface impoundment is divided into subcells to identify the location of leakage. The 

9 applicant may specify the threshold rate to identify leakage. A seepage collection and 

10 conveyance system consisting of perforated pipes has been placed at the bottom of leak 

11 detection layer. 

12

13 Cover Design

14

15 (15) Sufficient details of the proposed cover of the surface impoundments have 

16 been provided.

17

18 (a) Different material layers for the cover are described.

19

20 (b) Materials and their characteristics for each layer, including borrow areas from 

21 which the materials will be collected, are described.

22

23 (c) The geomembrane is described, if used, and its properties are provided. 

24

25 (d) The method of construction of the cover is described.

26

27 (e) A description of any vegetation and/or rock cover (riprap) is provided.

28

29 Procedures, specifications, and requirements for riprap, rock mulch, and filter production 

30 and placement are provided and are shown to be consistent with NUREG–1623, “Design 

31 of Erosion Protection for Long-Term Stabilization” (NRC, 2002), accepted engineering 

32 practice, and accepted design specifications (Walters, 1982). Soil or rock to be used for 

33 constructing cover materials does not contain elevated levels of radium.

34 Applicants should be aware of the research into actual field scale performance of 

35 engineered barrier cover systems (NRC, 2011). When considering cover design during 

36 the initial licensing of a conventional mill or heap leach facility, it may be beneficial to 

37 develop an understanding of long term behavior of the soil, rock, and vegetation 

38 conditions in the vicinity of the proposed site. Applicants may consider installation of 

39 instrumented test sections of various cover systems to collect on-site performance data 

40 supporting the selection of the final cover system at reclamation. 

41

42 Leachate Storage Pond in a Heap Leach Facility

43

44 (16) The design of the solution storage pond: 

45

46 (a) Has adequate capacity for collecting leachate solution and runoff from 

47 anticipated storm events.

48

49 (b) Has identified and adequately described materials for the liner of the solution 

50 storage pond.
Description and Design of Proposed Facility

3-19

1 (c) Contains side slopes that are relatively flat (i.e., generally not steeper than 3h:1v) 

2 (Strachan and Dorey, 1988). If a steeper slope is proposed, the applicant has 

3 provided technical justifications for such selection.

4

5 (d) Contains liner materials that are resistant to sunlight, anticipated temperature 

6 fluctuations, wave actions, chemical attack, and wind pressures; the applicant 

7 has provided sufficient information on the proposed liner system of the 

8 leachate storage pond for review using acceptance Criteria 12–14 of this section 

9 of the SRP.

10

11 (e) Demonstrates that permeability of the liner is acceptably low.

12

13 Barren Solution Pond in Heap Leach Facility

14

15 (17) The barren solution pond has a low-permeability liner and is adequate for effective 

16 containment, which will be reviewed using the acceptance Criteria 12–14 of this section 

17 of the SRP. The capacity of the pond is adequate to accommodate the anticipated 

18 maximum volume of barren solution during operation.

19

20 Other Types of Ponds

21

22 (18) Other types of ponds (e.g., evaporation ponds) have a low-permeability liner and 

23 are adequately designed for effective containment, which will be reviewed using the 

24 acceptance Criteria 12–14 of this section of the SRP. The capacities of the ponds 

25 are adequate to accommodate the anticipated maximum volume of solution 

26 during operation.

27

28 Dewatering of Tailings/Leachate Collection System

29

30 (19) The applicant has described an acceptable system to dewater the mill tailings to lower 

31 the phreatic surface and reduce the driving seepage head acting on the liner system. 

32 New surface impoundments should be dewatered by a drainage system to lower the 

33 pheretic surface (i.e., height of the saturated zone) above the liner system (NRC, 2008). 

34 The applicant has demonstrated the following: 

35

36 (a) The dewatering system of the surface impoundment is adequately sized to keep 

37 the height of the saturated zone to a minimum.

38

39 (b) Materials to be used for constructing the dewatering system are chemically 

40 compatible with the tailings.

41

42 (c) An analysis has demonstrated that the pipes, if used to dewater the tailings, will 

43 not be crushed or deflected significantly due to the weight of the tailings placed 

44 above so that the dewatering system will not lose effectiveness.

45

46 (20) The applicant has adequately described the design of the solution collection system to 

47 be used to collect and convey the leachate solution to the pregnant solution pond. The 

48 applicant has demonstrated the following: 

49

50 (a) Design of the solution collection system can accommodate the rate of flow of 

51 leachate in addition to runoff and seepage through the heap from anticipated 
Description and Design of Proposed Facility

3-20

1 storms. The applicant has provided adequate justification for selecting the 

2 extreme precipitation event to design the storage capacity.

3

4 (b) The applicant has demonstrated that design of the solution collection system 

5 would keep the height of the saturated zone (expected pheretic surface) above 

6 the liner to a minimum so that stability of the heap is not affected.

7

8 (c) Materials to be used to construct the collection pipes are chemically compatible 

9 with the leachate solution.

10

11 (d) An analysis has demonstrated that the collection pipes, if used to collect 

12 leachate, will not crush or deflect significantly due to the weight of the heap 

13 materials above them so that the solution collection system will remain effective.

14

15 (e) The solution collection system would be able to collect the liquid if rinsing or 

16 any special treatment of the leached ore is necessary before reclamation 

17 operation begins.

18

19 (f) Tests have been conducted to show that the load from heap leach materials 

20 would not significantly affect permeability of ore particles as the leaching 

21 operation progresses, thus requiring different filter characteristics (Ulrich, 

22 et al., 2003).

23

24 (21) The drains of the dewatering system in a surface impoundment or the leachate collection 

25 system in a heap leach pad will be protected by filter materials to prevent clogging so 

26 that the dewatering system remains free running. U.S. Department of Agriculture (1994) 

27 provides acceptable examples of designing soil filters. The capacity of the dewatering 

28 system has also been shown to be adequate.

29

30 Slope Stability

31

32 (22) The applicant has provided detailed information about the surface impoundment for 

33 assessing the slope stability. The information, at a minimum, includes:

34

35 (a) Detailed dimensions of the surface impoundment;

36

37 (b) All materials are identified and located in the drawings including any earthen or 

38 synthetic liner system and the cover system;

39

40 (c) Properties of each type of material based on laboratory and/or field 

41 measurements; these measurements were conducted using appropriate 

42 acceptable standards, such as American Society for Testing and Materials; and

43

44 (d) Height of the phreatic zone (i.e., height of the saturated zone) in the surface 

45 impoundment in addition to the height of the water table in the surrounding soil or 

46 rock mass.

47

48 (23) Cross sections and profiles of the surface impoundment are presented in sufficient 

49 number and detail to enable the staff to select the cross sections for detailed stability 

50 analysis or verification. Locations selected for slope stability analysis consider the 

51 location of maximum slope angle, slope height, foundation characteristics, groundwater 
Description and Design of Proposed Facility

3-21

1 levels, the extent of rock mass fracturing (for an excavated slope in rock), and the 

2 potential for local erosion including the effects of toe erosion, incision at the base of the 

3 slope, and other deleterious effects of surface runoff.

4

5 (24) An appropriate analytical method has been used to assess stability of a surface

6 impoundment or a heap leaching pad. Sufficient justification is provided for the selection 

7 of a two-dimensional or a three-dimensional method to estimate the safety of the slope. 

8 A plane strain analysis conducted in two dimensions along the maximum section of the 

9 slope may not adequately simulate the behavior under seismic load, especially for steep 

10 slopes (e.g., in steep canyons) and may result in an unsatisfactory design (Mejia and 

11 Seed, 1983). If a two-dimensional analysis is presented to demonstrate stability of the 

12 slopes, justification for not needing a three-dimensional analysis for the particular case is 

13 provided. Although in the vast majority of cases a two-dimensional analysis is 

14 satisfactory, the staff has examined the potential failure surface to assure that it is 

15 not constrained so that the plain strain assumption used in two-dimensional analyses 

16 is valid. Additionally, the applicant has justified the values(s) of the parameters used in 

17 the analysis.

18

19 For cases where seismic load is negligible, the method selected may be one of the limit 

20 equilibrium methods. A number of different methods of analysis are available (e.g., slip 

21 circle method, method of slices, and wedge analysis) with several variants of each 

22 (Lambe and Whitman, 1979; U.S. Army Corps of Engineers, 2003; NRC, 2008; 

23 Bromhead, 1992). The effect of the assumptions and limitations of the methods used is 

24 discussed and accounted for in the stability assessment. The limit equilibrium methods 

25 are acceptable only for slopes with relatively simple geometry and material variations. 

26 Appropriate conservatism has been incorporated in the analysis using the limit 

27 equilibrium methods. A full stability analysis requiring use of either finite element or finite 

28 difference methods has been used for complex slopes. Appropriate failure modes 

29 during and after construction have been identified. The appropriate limit equilibrium 

30 method has been used to determine the factor of safety against the identified failure 

31 mode, if a deterministic approach is used. The critical slip surface of the failure surface 

32 corresponding to the lowest factor of safety has been determined. The analysis takes 

33 into account the failure surfaces within the slopes, including those through the 

34 foundation, if any. 

35

36 If a probabilistic approach is used, an appropriate method has been used to estimate the 

reliability index1 37 β or, alternatively, the probability of unsatisfactory performance, Pup. In 

38 geotechnical disciplines, it is more appropriate to calculate Pup by using the reliability 

39 index β (U.S. Army Corps of Engineers, 2006). The reliability index β for a slope has 

40 been estimated using one of several techniques (e.g., First Order Reliability Method 

41 (FORM), Second Order Reliability Method (SORM), Monte Carlo method) (Baecher and 

42 Christian, 2003; Chowdhury, 2010; Wu, 2008). Technical justification has been provided 

43 if a different method has been used to estimate the reliability index or probability of 

44

 1

Reliability Index β is the “number of standard deviations by which the expected value of the factor of safety is away 

from the unsatisfactory performance condition or the factor of safety equaling one” (U.S. Army Corps of Engineers, 

2006). As the value of β increases, the impoundment becomes less likely to fail.
Description and Design of Proposed Facility

3-22

1 unsatisfactory performance. The analysis submitted by the applicant has considered 

2 the following:

3

4 (a) Appropriate failure surfaces have been considered to estimate the minimum 

5 reliability index value, β, for the slope. A search algorithm to identify the critical 

6 surface with β is provided in Hassan and Wolff (1999) and U.S. Army Corps of

7 Engineers (2006). As discussed in U.S. Army Corps of Engineers (2006), the 

8 failure surface associated with the minimum factor of safety may be significantly 

9 different from the failure surface associated with the minimum reliability index.

10

11 (b) An acceptable number of simulations were conducted to estimate the reliability 

12 index if a Monte Carlo method was used.

13

14 (25) The variability of the boundaries and the material properties of soil and rock types within 

15 and beneath the slope, and the uncertainties associated with the forces acting on the 

16 slope and the pore pressures acting within and beneath the slope were considered. 

17 Adverse conditions, such as high water levels from severe rain and the probable 

18 maximum flood, were evaluated.

19

20 (26) The applicant has selected the maximum credible earthquake for analyzing stability of 

21 the surface impoundment. The applicant has demonstrated that the surface 

22 impoundment is located a sufficient distance away from a capable fault, on which a 

23 maximum credible earthquake larger than that which the surface impoundment could 

24 reasonably be expected to withstand, might occur.

25

26 Appropriate analyses considering the effect of seismic ground motions on slope 

27 stability are presented. A seismic load on a slope can develop significant inertial forces, 

28 causing instability or permanent deformation of the slope. Current practice is to use 

29 either a limit equilibrium method using a pseudostatic representation of the seismic 

30 forces or a displacement-based analysis using either the Newmark sliding block concept 

31 (Newmark, 1965) or rigorous numerical modeling methods (e.g., finite element or finite 

32 difference methods) (Transportation Research Board, 2008). The applicant has 

33 considered the following in the analysis to assess the effect of seismic ground motions 

34 on slope stability, as appropriate:

35

36 (a) The overall seismic stability was evaluated using pseudostatic analysis or 

37 dynamic analysis, as appropriate (U.S. Army Corps of Engineers, 1995a; NRC, 

38 2008). Alternatively, a dynamic analysis following Newmark (1965) was carried 

39 out to establish that the permanent deformation of the disposal cell from the 

40 design seismic event would not be detrimental to the disposal cell. The yield 

41 acceleration or pseudostatic horizontal yield coefficient necessary to reduce the 

42 factor of safety against slippage of a potential sliding mass to 1.0 in a 

43 “Newmark-type” analysis has been adequately estimated (Seed and 

44 Bonaparte, 1992).

45

46 (b) For dynamic loads, the dynamic analysis includes calculations with appropriate 

47 assumptions and methods (NRC, 2008; Seed, 1967; Department of the Navy, 

48 1986a,b, 1997; U.S. Army Corps of Engineers, 1986, 1995a, 2001, 2003; Bureau 

49 of Reclamation, 1998). The effect of the assumptions and limitations of the 

50 method(s) used are discussed in the analysis.

51
Description and Design of Proposed Facility

3-23

1 (c) Degradation of dynamic shear strength of cohesive soils due to repeated 

2 cycles of earthquake loading has been appropriately considered following the 

3 American Society of Testing and Materials Society or other acceptable standards 

4 (e.g., ASTM International, 2007b, 2003).

5

6 For dynamic loads, a pseudostatic analysis was performed in lieu of dynamic 

7 analysis if the strength parameters used in the analysis are conservative, the 

8 materials are not subject to significant loss of strength and development of high 

9 pore pressures under dynamic loads, the design seismic coefficient is 0.20 or 

10 less, and the resulting minimum factor of safety suggests an adequate margin 

11 consistent with Regulatory Guide 3.11, Revision 3 (NRC, 2008).

12

13 (d) For pseudostatic analysis of slopes subjected to earthquake loads, an 

14 assumption is made that the earthquake imparts additional horizontal force acting 

15 in the direction of the potential failure (U.S. Army Corps of Engineers, 2003, 

16 1995a; Goodman, 1989). The critical failure surface obtained in the static 

17 analysis is used in this analysis with the added driving force. The estimated 

18 safety factors for slopes analyzed using a deterministic approach are consistent 

19 with the minimum acceptable values of safety factors for slope stability analysis 

20 consistent with Regulatory Guide 3.11, Revision 3 (NRC, 2008).

21

22 (e) The influence of local site conditions on the ground motions associated with the 

23 design level event was evaluated. 

24

25 (f) The applicant has justified the design seismic coefficient used in the pseudostatic 

26 analysis. The seismic coefficient is generally expressed as a fraction of the peak 

27 ground acceleration and typically ranges from less than 50 percent to peak 

28 ground acceleration (Anderson, et al., 2008). If the design seismic coefficient is 

29 greater than 0.20 g, then the dynamic stability investigation (Newmark, 1965) has 

30 been augmented by other appropriate methods (i.e., finite element method, finite 

31 difference method) depending on specific site conditions.

32

33 (g) If a pseudostatic stability analysis using limit equilibrium methods is used to 

34 assess the effects of seismic loads on slope stability, the effect of dynamic or 

35 cyclic stresses of the design earthquake on soil strength parameters and 

36 damping is determined. Use of static undrained strength in the analysis may be 

37 acceptable if the potential increase in undrained strength during the first cycle of 

38 loading could be negated by degradation of strength after 10 to 15 cycles 

39 (Anderson, et al., 2008; Seed, et al., 1986). Alternatively, measured strength 

40 under cyclic loading has been provided if the use of static undrained strength is 

41 questionable. As in a static analysis, the parameters such as geometry, soil 

42 strength, and hydrodynamic and pore pressure forces are varied in the analysis 

43 to show that there is an adequate margin of safety.

44

45 (h) If a displacement-based approach [e.g., Newmark (1965) method or its 

46 modification, finite element/finite difference methods] is used to assess stability, 

47 the appropriate site peak ground acceleration coefficient and yield acceleration 

48 (i.e., seismic coefficient for a factor of safety equal to 1.0) was used in the 

49 assessment. Seismically induced displacement is calculated and documented. 

50 The acceptable performance of the disposal cell is consistent with Seed and 

51 Bonaparte (1992) and Goodman and Seed (1966). Seed and Bonaparte (1992) 
Description and Design of Proposed Facility

3-24

1 indicate that the acceptable displacement should be 15 cm [6 in] or less. In rare 

2 cases, a permanent displacement of 30 cm [12 in] or less may be acceptable if a 

3 conservative analysis is used and the tailings impoundment can be demonstrated 

4 to undergo such permanent displacement without adverse consequences. The 

5 applicant has justified the acceptable permanent displacement value, which 

6 would not produce adverse consequences, and the license application is also 

7 augmented by provisions for periodic maintenance of the slope(s).

8

9 (i) Where there is potential for liquefaction, changes in pore pressure from cyclic 

10 loading are considered in the analysis to assess the effect of pore pressure 

11 increase on the stress-strain characteristics of the soil and the post-earthquake 

12 stability of the slopes. Evaluations of the dynamic properties and shear strengths 

13 for the tailings, underlying foundation material, and base liner system are based 

14 on representative material properties obtained through appropriate field and 

15 laboratory tests.

16

17 (27) The applicant has considered reasonable ranges of the parameters if the estimated 

18 safety margin (i.e., estimated factor of safety or reliability index) is low. Additionally, the 

19 applicant has considered other factors, such as flooding conditions, pore pressure 

20 effects, possible material erosion, and seismic amplification, in the stability assessment. 

21 The degree of conservatism necessary depends on the type of analysis used, and 

22 variabilities and uncertainties associated with the parameters.

23

24 (28) The stability of the surface impoundments is appropriately demonstrated following 

25 guidance in Regulatory Guide 3.11, Revision 3 (NRC, 2008) if a deterministic approach 

26 is used. However, accepted values of the reliability index β or the probability of 

27 unsatisfactory performance Pup has not been established yet. Only a few publications 

28 provide a minimum acceptable value of β (e.g., Chowdhury, 2010, pp. 541–542). 

29 Therefore, the applicant justifies why the estimated β or Pup would be acceptable given 

30 the potential consequence in case of a failure.

31

32 (29) Any dike (or dam) meets the requirements of the federal dam safety program if the 

33 application demonstrates the following:

34

35 (a) The dike is correctly categorized as a low hazard potential or a high hazard 

36 potential structure using the definition of the U.S. Federal Emergency 

37 Management Agency (1998).

38

39 (b) If the dike is ranked as a high hazard potential, an acceptable emergency action 

40 plan consistent with the Federal Emergency Management Agency guide 

41 (U.S. Federal Emergency Management Agency, 1998) has been developed.

42

43 Liquefaction

44

45 (30) The results of site exploration, geotechnical investigations, and in-situ tests, such as 

46 standard penetration, cone penetration, piezocone, density, and strength tests as well as 

47 boring logs, laboratory classification test data, water table measurements, perched water 

48 zones, and soil profiles, are adequate to ensure that the site soils beneath the site and 

49 the surface impoundments are not susceptible to liquefaction. Applicable laboratory 

50 and/or field tests were properly conducted (NRC, 2003a,b; U.S. Army Corps of 

51 Engineers, 1986, 2001) using acceptable standards, such as those of the American 
Description and Design of Proposed Facility

3-25

1 Society for Testing and Materials. Data for all relevant parameters for assessing 

2 liquefaction potential are adequately presented, and their variabilities have been 

3 quantified. The time history of earthquake ground motions used in the analysis is 

4 consistent with the design seismic event.

5

6 Preliminary evaluation of liquefaction potential considers the following site characteristics 

7 identified in Regulatory Guide 1.198, “Procedures and Criteria for Assessing Seismic 

8 Soil Liquefaction at Nuclear Power Plant Sites” (NRC, 2003c), Youd, et al. (2001) 

9 Ferritto (1997), and Seed, et al. (2003): (i) whether potentially liquefiable soils are 

10 present beneath the surface impoundment, (ii) whether the liquefiable soils are saturated 

11 or could become saturated in the future, and (iii) whether the thicknesses or lateral 

12 extent of these soils sufficient to pose a risk to the project. The applicant demonstrates 

13 an understanding of whether the soils present are liquefiable or the surface 

14 impoundments are stable. The soil screening criteria include the following 

15 characteristics (NRC, 2008; Koester, et al., 2000):

16

17 (a) Geologic age and origin;

18 (b) Fines contents and plasticity index;

19 (c) Saturation;

20 (d) Depth below the ground surface; and

21 (e) Penetration resistance.

22

23 If the screening evaluation did not definitively address whether the soil is liquefiable, 

24 detailed evaluations were conducted in accordance with Acceptance Criterion 31.

25

26 (31) The liquefaction potential has been characterized using appropriate methods, including 

27 analysis of minor or local liquefaction. Appropriate measures have been proposed to 

28 mitigate or eliminate the effects of liquefaction, when necessary.

29

30 (a) If the potential for complete or partial liquefaction exists, the effects such 

31 liquefaction has on the stability of slopes and settlement of tailings are 

32 adequately quantified. Assessment of the liquefaction potential is consistent with 

33 current practice in the geotechnical engineering profession (e.g., Seed and Idriss, 

34 1971, 1982; National Center for Earthquake Engineering Research, 1997; Youd, 

35 et al., 2001; Idriss and Boulanger, 2004). Two broad classes of methods are 

36 used: (i) empirical procedures; and (ii) analytical methods. Currently, four in-situ

37 test methods have been widely used: (i) Standard Penetration Test (SPT) 

38 (Seed, et al., 2003; Seed and Harder, 1990; Cetin, et al., 2000, 2004); (ii) Cone 

39 Penetration Test (Seed ,et al., 2003; Moss, et al., 2006); (iii) measurement of 

40 in-situ shear wave velocity (Seed, et al., 2003); and (iv) Becker Penetration Test 

41 (BPT) (Seed, et al., 2003; U.S. Army Corps of Engineers, 2001). Applicability of 

42 these test methods in assessing liquefaction potential is discussed in Youd, et al. 

43 (2001) and Regulatory Guide 1.198 (NRC, 2003c). The estimated factor of 

44 safety is consistent with Regulatory Guide 1.198 (NRC, 2003c). Analytical 

45 methods typically use laboratory test results to assess development of 

46 liquefaction. An assessment of the potential adverse effects that complete or 

47 partial liquefaction could have on the stability of the embankment may be based 

48 on cyclic strength test data obtained from undisturbed soil samples taken from 

49 the critical zones in the site area (Seed and Harder, 1990). Uncertainties 

50 associated with the parameter values are addressed consistent with Regulatory 

51 Guide 1.198 (NRC, 2003c). If procedures based on laboratory tests combined 
Description and Design of Proposed Facility

3-26

1 with ground response analyses were used, laboratory test results were corrected 

2 to account for the difference between laboratory and field conditions (NRC, 

3 2003b; Department of Navy, 1997). Guidelines for laboratory testing are 

4 described in Regulatory Guide 1.138, “Laboratory Investigations of Soils for 

5 Engineering Analysis and Design of Nuclear Power Plants,” Revision 2 

6 (NRC, 2003b). The applicant may use procedures that are alternative to those 

7 suggested in these documents, provided appropriate justification has been 

8 provided for their use.

9

10 (b) If probabilistic methods are used to assess liquefaction potential, the 

11 methodology is consistent with the current practice (e.g., Hynes, 1999; 

12 Cetin, et al., 2002; Juang, et al., 2006). The probability of liquefaction on 

13 reliability index β is consistent with the current engineering practice and is 

14 technically justified.

15

16 (c) If a potential for major liquefaction is identified, mitigation measures consistent 

17 with current engineering practice or redesign of surface impoundment 

18 embankments are proposed and the proposed measures provide reasonable 

19 assurance that the liquefaction potential has been eliminated or mitigated.

20

21 (d) If minor liquefaction potential is identified and is evaluated to have only a 

22 localized effect that may not directly alter the stability of embankments, the effect 

23 of liquefaction is adequately assessed in analyses of both differential and total 

24 settlement and is shown not to compromise the intended performance of the 

25 radon barrier. Additionally, the disposal cell is shown to be capable of 

26 withstanding the liquefaction potential associated with the expected maximum 

27 ground acceleration from earthquakes. The licensee may use post-earthquake 

28 stability methods (e.g., Ishihara and Yoshimine, 1990) based on residual 

29 strengths and deformation analysis to examine the effects of liquefaction 

30 potential. Furthermore, the effect of potential localized lateral displacement from 

31 liquefaction, if any, is adequately analyzed with respect to slope stability and 

32 disposal cell integrity (e.g., Bardet, et al., 1999; Koester, et al., 2000; Seed, 

33 et al., 2003).

34

35 Settlement

36

37 (32) The method used for settlement analysis is appropriate for the surface impoundment 

38 and soil conditions at the site. Contributions to settlement by drainage of mill tailings 

39 and by consolidation/compression of slimes and sands are considered for the surface 

40 impoundment. Similarly, contributions to settlement by drainage of leachate and any 

41 rinsing solution, if used, and consolidation/compression of the leached ore by cover 

42 placement operations in a heap leach pad are appropriately considered. Both 

43 instantaneous and time-dependent components of total and differential settlements are 

44 appropriately considered in the analyses (Nelson, et al., 1983a, b). Calculation of 

45 immediate settlement and secondary compression is consistent with the standard 

46 procedures [e.g., those recommended in NAVFAC DM 7.1 (Department of the Navy, 

47 1986a) and U.S. Army Corps of Engineers (1990)]. If different procedures are used, the 

48 basis for the procedures is justified. Properties used in calculating settlement are 

49 measured using appropriate testing standards [e.g., ASTM International (2004, 2007c)]. 

50 The magnitude and the rate of the expected settlement of the embankment and the 

51 radon barrier cover are estimated using the results of consolidation tests conducted in 
Description and Design of Proposed Facility

3-27

1 the laboratory on samples from embankment materials, foundation, and tailings. 

2 However, significant uncertainties exist in the estimated time for settlement because 

3 settlement in the field is affected by soil drainage (NRC, 2008), which is controlled by 

4 small-scale geological details. Generally, site investigations may not be able to 

5 capture these small-scale details adequately. Therefore, the applicant may need to 

6 modify the settlement predictions, which is based on laboratory-measured data, using 

7 actual measurements.

8

9 (a) Each of the following is appropriately considered in calculating stress increments 

10 for assessment of consolidation settlement:

11

12 (i) Decrease in overburden pressure from excavation, if any;

13 (ii) Increase in overburden pressure from tailings emplacement;

14 (iii) Excess pore pressure generated within the surface impoundment; or

15 (iv) Changes in water levels from dewatering of the tailings.

16

17 (b) Material properties and thicknesses of compressible soil/rock layers used in 

18 stress change and volume change calculations for assessment of consolidation 

19 settlement are representative of in-situ conditions at the site.

20

21 (c) Values of pore pressure within and beneath the disposal cell used in settlement 

22 analyses are consistent with initial and postconstruction hydrologic conditions at 

23 the site.

24

25 (33) The applicant has provided the expected instantaneous and long-term settlement 

26 magnitudes for the embankment. The magnitude of anticipated total settlement is 

27 small enough so that sufficient freeboard will be available to prevent overtopping 

28 from operations, overfilling, wind and wave actions, rainfall or run-on, malfunction of 

29 level controllers and other equipment, and human error. Additionally, differential 

30 settlement is within tolerable limits so that cracks will not develop, affecting the integrity 

31 of the embankment.

32

33 (34) The surface impoundment will be divided into appropriate zones, depending on field 

34 conditions, for assessment of differential settlement and the overall settlement pattern of 

35 the disposal cell of the surface impoundment. 

36

37 The applicant has estimated the time at which the settlement, due to primary 

38 consolidation of the mill tailings or leached ore, will be essentially complete. The 

39 applicant proposes to place the radon barrier and disposal cell cover after this time.

40

41 Results of settlement analyses are properly documented. The magnitudes of total and 

42 differential settlement are within the tolerable limits of the engineered components of the 

43 surface impoundment [e.g., clay liners, geomembranes (if used), drainage layers, and 

44 pipes] so that cracks will not develop affecting their intended safety function. An 

45 adequate analysis is provided of the potential for development of cracks in the 

46 radon/infiltration barrier because of differential settlement.

47

48 Construction

49

50 (35) The planned configuration will have adequate capacity to accommodate all leached 

51 materials and other contaminated materials throughout the planned lifecycle of the 
Description and Design of Proposed Facility

3-28

1 facility including any alternate feed of materials from other facilities. Uncertainties in the 

2 estimated volume of contaminated materials can be accommodated.

3

4 (36) The applicant has provided a detailed plan for constructing the surface impoundment 

5 that includes construction specifications for areas such as excavation, embankment 

6 construction, subgrade preparation, and liner placement. The following were considered 

7 as minimum guidelines, with the understanding that additional or more stringent 

8 specifications may be required depending on site conditions at individual sites:

9

10 (a) Engineering drawings at appropriate scales clearly show the design features 

11 with appropriate dimensions.

12

13 (b) A geotechnical or construction inspector will be onsite during 

14 embankment construction.

15

16 (c) Materials to be used for each feature of the facility are identified.

17

18 (d) Source, quality, and quantities of borrow materials, if needed in the construction, 

19 are identified. The borrow materials, if needed, have been characterized using 

20 field and laboratory tests for use in constructing the surface impoundment. The 

21 background level of contamination of the borrow materials, if needed, has been 

22 adequately established. Borrow materials will be taken from an approved, 

23 designated borrow area that is free of roots, stumps, wood, rubbish, stones 

24 greater than 15 cm [6 in], and frozen or other objectionable materials.

25

26 (e) Areas on which fill is to be placed will be scarified before its placement.

27

28 (f) Methods, procedures, and requirements for excavating, hauling, and stockpiling 

29 of contaminated and noncontaminated materials have been provided and have 

30 been shown to be consistent with commonly accepted engineering practice for 

31 earthen works (Department of Navy, 1997, 1986b; U.S. Army Corps of 

32 Engineers, 2008, 2004, 1995b; U.S. Department of Agriculture, 2008).

33

34 (g) Procedures, specifications, and requirements for riprap, rock mulch, and filter 

35 production and placement have been provided and have been shown to be 

36 consistent with NUREG–1623 (NRC, 2002) and accepted engineering practice 

37 (Walters, 1982).

38

39 (h) The construction sequence has been described and demonstrated to be 

40 adequate to achieve the intended configuration and characteristics for the 

41 surface impoundment and associated other components of facility.

42

43 (i) The method of placement of tailings in the surface impoundments has been 

44 adequately described. The description also includes the equipment to be used 

45 and the method of placing the tailings. For a heap leach facility, the applicant 

46 has provided the method (e.g., dumping with dozer leveling, conveyor stacking) 

47 and equipment to be used in constructing the heap leach pad. Additionally, the 

48 method (e.g., flooding or ponding, pressure emitters, “wobblers,” “wigglers”) and 

49 application rate of the leaching solution to the heap have been provided 

50 (Muhtadi, 1988).

51
Description and Design of Proposed Facility

3-29

1 (j) Appropriate quality control provisions have been provided to ensure that the 

2 construction will be in accordance with the plan. The descriptions of the 

3 methods, procedures, and frequencies by which the construction materials and 

4 activities are to be tested and inspected are reasonable, and appropriate records 

5 will be maintained (Johnson, et al., 1983).

6

7 (k) The schedule to complete the construction activities has been provided.

8

9 (37) Material placement and compaction procedures are adequate to achieve the desired 

10 moisture content, placement density, and permeability and will follow an accepted 

11 standard, such as U.S. Army Corps of Engineers (1995b) and recommendations made 

12 in NUREG/CR–5041 (Denson, et al., 1987). Compaction specifications include 

13 restriction on work during adverse weather conditions (e.g., rainfall, freezing 

14 conditions) and include season and duration of the construction activities as they 

15 affect the moisture content.

16

17 The compaction requirements for the borrow materials will include the maximum dry 

18 density, allowable range of moisture content, and maximum loose lift thickness. Borrow 

19 materials will be compacted with appropriate compaction equipment (e.g., sheepsfoot, 

20 rubber tired, or vibratory roller). The number of passes required by the compaction 

21 equipment may vary with soil conditions. Borrow materials will contain sufficient 

22 moisture to develop the required degree of compaction by the equipment to be used. 

23 Field density tests will be performed regularly throughout the embankment construction. 

Typically, a routine control test will be performed for every 765 to 2,294 m3 24 (1,000 to 

3,000 yd3 25 ) of compacted material and as directed by the geotechnical engineer 

26 consistent with Regulatory Guide 3.11, Revision 3 (NRC, 2008). The applicant has 

27 proposed adequate quality control techniques to verify material placement, 

28 including geosynthetics. 

29

30 (38) The subgrade will be adequately prepared for installing the liner system. The site will be 

31 cleared of all debris, vegetation, and potential root systems. The surface will be graded 

32 so that it is smooth and free of protruding rock particles. The applicant has provided 

33 sufficient information on the proposed construction procedures, which includes 

34 provisions for modification of moisture condition of subgrade soil, if necessary.

35

36 (39) Seams of a synthetic liner will run up and down and not across a slope unless the 

37 applicant has provided a technical justification. Additionally, seams will not be located 

38 near the crest of a slope consistent with Regulatory Guide 3.11, Revision 3 (NRC, 2008). 

39 Seaming will be carried out under supervision of experienced personnel. The applicant 

40 will test the seams of the synthetic liner system, if used, for integrity along the entire 

41 length using appropriate test procedures (e.g., ASTM, 2010; 2009c,d; 2008b,c,d; 2007c; 

42 2006a,b,c). The testing procedures follow the manufacturer’s recommendations for the 

43 liner system.

44

45 Inspection and Monitoring 

46

47 (40) A plan to inspect the conditions and adequacy of the surface impoundment, including 

48 access during routine maintenance, has been described. The procedure assures that 

49 unnecessary traffic is not directed to the impoundment/leach area. The inspection 

50 program uses a qualified engineer or scientist, and the applicant commits to 

51 documenting the inspections. The NRC staff considers that a person with a 4-year 
Description and Design of Proposed Facility

3-30

1 engineering or science degree could be designated as a qualified engineer or scientist. 

2 The inspection and monitoring program will start at the beginning of construction and will 

3 be consistent with the guidance provided in Regulatory Guide 3.11, Revision 3 

4 (NRC, 2008).

5

6 (41) The applicant has proposed acceptable inspection frequencies of important elements 

7 of surface impoundments. Additionally, the applicant has described the instrumentation 

8 and procedures to inspect the facilities following a recognized standard, such as 

9 U.S. Army Corps of Engineers (1995c). Available records and readings of these 

10 instruments will be reviewed to detect any unusual performance or distress of 

11 the structure.

12

13 The proposed frequency of inspection of each element of the retention system is 

14 commensurate with the size, characteristics of the foundation, and consequence of 

15 failure of the element to minimize jeopardizing human health and safety and causing 

16 environmental and property damage.

17

18 The scope of a special inspection after a major event is commensurate with the severity 

19 of the event. For example, an inspection would be made after a major nearby 

20 earthquake to assess the integrity of the dike and the impoundment. Similarly, after 

21 a major rainfall event, the impoundments would be inspected for breach, overtopping, 

22 and containment release.

23

24 3.3.4 Evaluation Findings

25

26 If the staff determines that no license conditions are required for the design of surface

27 impoundments because the applicant or licensee provided adequate and complete information 

28 that fully addresses all relevant regulatory requirements, typically a single paragraph is needed 

29 for the evaluation findings section. Begin the section with the sentence: “NRC staff has 

30 completed its review of the design of surface impoundments at the conventional uranium 

31 millheap leach facility in accordance with Section 3.3.3 of the standard review plan.” Following 

32 this sentence, state what information the applicant provided in the application. As discussed in 

33 the introduction of this SRP, a bullet or sentence format may be used to list what information the 

34 applicant has provided. 

35

36 After the description of the information the applicant provided, the following or a similar 

37 statement can be added: “Based on the review conducted by NRC staff, the information 

38 provided in the application meets the applicable acceptance criteria of Section 3.3.3 of the 

39 standard review plan. Therefore, NRC staff concludes that the applicant’s design of surface

40 impoundments is acceptable and is in compliance with 10 CFR 40.27(b)(2), which requires a 

41 detailed description of the final disposal site conditions; 10 CFR 40.31(h), which establishes 

42 requirements for license applications; 10 CFR Part 40, Appendix A, Criterion 1, which requires 

43 permanent isolation of tailings and associated contaminants by minimizing disturbances and 

44 dispersion by natural forces; 10 CFR Part 40, Appendix A, Criterion 3, which prescribes the 

45 preferred option for disposal of tailings below the grade and reasonable isolation of the tailings 

46 from natural erosional forces; 10 CFR Part 40, Appendix A, Criterion 4(a), which requires that 

47 upstream catchment areas be minimized; 10 CFR Part 40, Appendix A, Criterion 4(b), which 

48 requires that topographic features should provide good wind protection; 10 CFR Part 40, 

49 Appendix A, Criterion 4(c), which specifies final embankment cover slopes be relatively flat; 

50 10 CFR Part 40, Appendix A, Criterion 4(d), which prescribes a self-sustaining vegetative or 

51 rock cover to reduce wind and water erosion to negligible levels; and 10 CFR Part 40, 
Description and Design of Proposed Facility

3-31

1 Appendix A, Criterion 4(e), which prescribes that the surface impoundments should be 

2 constructed away from capable faults.”

3

4 In addition, add: “NRC staff concludes that the applicant’s design of surface impoundments is 

5 also in compliance with 10 CFR Part 40, Appendix A, Criterion 5A(1), which requires a liner 

6 system to prevent migration of waste; 10 CFR Part 40, Appendix A, Criterion 5A(2), which 

7 requires that the liner to be installed has sufficient strength, an adequate foundation for the liner, 

8 and that the liner covers all surrounding earth likely to be in contact with the waste or leachate; 

9 10 CFR Part 40, Appendix A, Criterion 5A(3), which allows for alternate designs and operating 

10 practices if the Commission approves; 10 CFR Part 40, Appendix A, Criterion 5A(4), which 

11 requires prevention of overtopping; 10 CFR Part 40, Appendix A, Criterion 5A(5), which 

12 prescribes that the dikes for the impoundments should be designed, constructed, and 

13 maintained to have sufficient structural integrity; 10 CFR Part 40, Appendix A, Criterion 5E(1), 

14 which requires a bottom liner; 10 CFR Part 40, Appendix A, Criterion 5E(3), which requires 

15 dewatering of tailings; 10 CFR Part 40, Appendix A, Criterion 5G(2), which prescribes the 

16 required characteristics of the subgrade; 10 CFR Part 40, Appendix A, Criterion 6(1), which 

17 requires an earthen cover over the tailings; 10 CFR Part 40, Appendix A, Criterion 6(5), which

18 prescribes that the near-surface cover materials should not have elevated levels of radium; and 

19 10 CFR Part 40, and Appendix A, Criterion 6A(3), which authorizes a licensee to dispose of 

20 byproduct or similar materials from other sources if appropriate criteria are met.”

21

22 In addition, add: “NRC staff concludes that the applicant’s design of surface impoundments is 

23 also in compliance with 10 CFR Part 40, Appendix A, Criterion 8A, which requires daily 

24 inspections of tailings retention systems; and the requirements of the Federal Dam Safety 

25 Program of the U.S. Federal Emergency Management Agency if the hazard potential of the 

26 surface impoundment is high.” As a concluding statement, indicate the reason why the 

27 applicant’s information is considered adequate and complete, and why or how that information 

28 complies with the identified regulatory requirements.

29

30 If license conditions are needed, then a more detailed discussion is typically required. Begin 

31 this section with the sentence: “NRC staff has completed its review of the design of surface

32 impoundments at the conventional uranium millheap leach facility in accordance with 

33 Section 3.3.3 of the standard review plan.” Following this sentence, state what information the 

34 applicant provided in the application, including identification of the information that was omitted 

35 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

36 used to list what information the applicant has provided. Next, state why a license condition is 

37 needed, followed by the license condition or conditions. 

38

39 In a separate paragraph following the discussion of the required license condition(s), include the 

40 statement: “Based on the review conducted by NRC staff, the information provided in the 

41 application, supplemented by provisions of the license condition(s) discussed above, meets the 

42 applicable acceptance criteria of Section 3.3.3 of the standard review plan. Therefore, NRC 

43 staff concludes that the applicant’s design of surface impoundments is acceptable and is in 

44 compliance with 10 CFR 40.27(b)(2), which requires a detailed description of the final disposal 

45 site conditions; 10 CFR 40.31(h), which establishes requirements for license applications; 

46 10 CFR Part 40, Appendix A, Criterion 1, which requires permanent isolation of tailings and 

47 associated contaminants by minimizing disturbances and dispersion by natural forces; 

48 10 CFR Part 40, Appendix A, Criterion 3, which prescribes the preferred option for disposal of 

49 tailings below the grade and reasonable isolation of the tailings from natural erosional forces;

50 10 CFR Part 40, Appendix A, Criterion 4(a), which requires that upstream catchment areas be 

51 minimized; 10 CFR Part 40, Appendix A, Criterion 4(b), which requires that topographic features 
Description and Design of Proposed Facility

3-32

1 should provide good wind protection; 10 CFR Part 40, Appendix A, Criterion 4(c), which 

2 specifies embankment cover slopes be relatively flat; 10 CFR Part 40, Appendix A, Criterion 

3 4(d), which prescribes a self-sustaining vegetative or rock cover to reduce wind and water 

4 erosion to negligible levels; and 10 CFR Part 40, Appendix A, Criterion 4(e), which prescribes 

5 that the surface impoundments should be constructed away from capable faults.”

6

7 In addition, add: “NRC staff concludes that the applicant’s design of surface impoundments is 

8 also in compliance with 10 CFR Part 40, Appendix A, Criterion 5A(1), which requires a liner 

9 system to prevent migration of waste; 10 CFR Part 40, Appendix A, Criterion 5A(2)(a), which 

10 requires that the liner to be installed has sufficient strength; 10 CFR Part 40, Appendix A,

11 Criterion 5A(2)(b), which requires an adequate foundation for the liner; 10 CFR Part 40, 

12 Appendix A, Criterion 5A(2)(c), which requires the liner to cover all surrounding earth likely to be 

13 in contact with the waste or leachate; 10 CFR Part 40, Appendix A, Criterion 5A(3), which allows 

14 for alternate designs and operating practices if the Commission approves; 10 CFR Part 40, 

15 Appendix A, Criterion 5A(4), which requires prevention of overtopping; 10 CFR Part 40, 

16 Appendix A, Criterion 5A(5), which prescribes that the dikes for the impoundments should be 

17 designed, constructed, and maintained to have sufficient structural integrity; 10 CFR Part 40, 

18 Appendix A, Criterion 5E(1), which requires a bottom liner; 10 CFR Part 40, Appendix A,

19 Criterion 5E(3), which requires dewatering of tailings; 10 CFR Part 40, Appendix A, 

20 Criterion 5G(2), which prescribes the required characteristics of the subgrade; 10 CFR Part 40, 

21 Appendix A, Criterion 6(1), which requires an earthen cover over the tailings; 10 CFR Part 40; 

22 10 CFR Part 40, Appendix A, Criterion 6(5), which prescribes that the near-surface cover 

23 materials should not have elevated levels of radium; 10 CFR Part 40, 10 CFR Part 40, 

24 Appendix A, Criterion 6A(3), which authorizes a licensee to dispose of byproduct or similar 

25 materials from other sources if appropriate criteria are met; 10 CFR Part 40, Appendix A,

26 Criterion 8A which requires daily inspections of tailings retention systems; and the requirements 

27 of the Federal Dam Safety Program of the U.S. Federal Emergency Management Agency if the 

28 hazard potential of the surface impoundment is high.” If not already discussed in the preceding 

29 paragraph(s), include a statement or summation as to why or how the application and license 

30 condition(s) jointly comply with the identified regulatory requirements.

31

32 3.3.5 References

33

34 Anderson, D.G., G.R. Martin, I. Lam, and J.N. Wang. “Seismic Analysis and Design of 

35 Retaining Walls, Buried Structures, Slopes, and Embankments.” NCHRP Report 611. National 

36 Cooperative Highway Research Program. Washington, DC: Transportation Research Board. 

37 2008.

38

39 ASTM International. “Standard Test Method for Tensile Properties of Plastics.” ASTM Standard 

40 D638–10. West Conshohocken, Pennsylvania: ASTM International. 2010.

41

42 –––––. “Standard Practice for Immersion Procedures for Evaluating the Chemical Resistance of 

43 Geosynthetics to Liquids.” ASTM Standard D5322–98. West Conshohocken, Pennsylvania: 

44 ASTM International. 2009a.

45

46 –––––. “Standard Practice for In Field Immersion Testing of Geosynthetics.” ASTM Standard

47 D5496–98. West Conshohocken, Pennsylvania: ASTM International. 2009b.

48

49 –––––. “Standard Test Method for Tear Resistance (Graves Tear) of Plastic Film and 

50 Sheeting.” ASTM Standard D1004-08. West Conshohocken, Pennsylvania: ASTM 

51 International. 2009c.
Description and Design of Proposed Facility

3-33

1 –––––. “Standard Test Method for Trapezoid Tearing Strength of Geotextiles.” ASTM Standard 

2 D4533–04. West Conshohocken, Pennsylvania: ASTM International. 2009d.

3

4 –––––. “Standard Practice for Tests to Evaluate the Chemical Resistance of Geomembranes to 

5 Liquids.” ASTM Standard D5747–08. West Conshohocken, Pennsylvania: ASTM 

6 International. 2008a.

7

8 –––––. “Standard Practice for Determining the Integrity of Field Seams Used in Joining Flexible 

9 Polymeric Sheet Geomembranes.” ASTM Standard D4437–08. West Conshohocken, 

10 Pennsylvania: ASTM International. 2008b.

11

12 –––––. “Standard Test Method for Determining the Integrity of Nonreinforced Geomembrane 

13 Seams Produced Using Thermo-Fusion Methods.” ASTM Standard D6392–08. West 

14 Conshohocken, Pennsylvania: ASTM International. 2008c.

15

16 –––––. “Standard Practice for Ultrasonic Testing of Geomembranes.” ASTM Standard D7006–

17 03. West Conshohocken, Pennsylvania: ASTM International. 2008d.

18

19 –––––. “Standard Test Method for Index Puncture Resistance of Geomembranes and Related 

20 Products.” ASTM Standard D4833–07. West Conshohocken, Pennsylvania: ASTM 

21 International. 2007a.

22

23 –––––. “Standard Test Methods for Prebored Pressuremeter Testing in Soils.” ASTM Standard 

24 D4719–07. West Conshohocken, Pennsylvania: ASTM International. 2007b.

25

26 –––––. “Standard Test Method for Modulus and Damping of Soils by Resonant-Column 

27 Method.” ASTM Standard D4015–07. West Conshohocken, Pennsylvania: ASTM 

28 International. 2007c.

29

30 –––––. “Standard Test Method for Measuring the Nominal Thickness of Geosynthetics.” ASTM 

31 Standard D5199–11. West Conshohocken, Pennsylvania: ASTM International. 2006a.

32

33 –––––. “Standard Practice for Geomembrane Seam Evaluation by Vacuum Chamber.” ASTM 

34 Standard D5641-94. West Conshohocken, Pennsylvania: ASTM International. 2006b.

35

36 –––––. “Standard Practice for the Nondestructive Testing of Geomembrane Seams Using the 

37 Spark Test.” ASTM Standard D6365–99. West Conshohocken, Pennsylvania: ASTM 

38 International. 2006c.

39

40 –––––. “Standard Test Methods for One-Dimensional Consolidation Properties of Soils Using 

41 Incremental Loading.” ASTM Standard D2435–04. West Conshohocken, Pennsylvania: ASTM 

42 International. 2004.

43

44 –––––. “Standard Test Method for the Determination of the Modulus and Damping Properties of 

45 Soils Using the Cyclic Triaxial Apparatus.” ASTM Standard D3999–91. West Conshohocken, 

46 Pennsylvania: ASTM International. 2003.

47

48 Baecher, G.B. and J.T. Christian. Reliability and Statistics in Geotechnical Engineering. 

49 Chichester, England: John Wiley & Sons Ltd. 2003.

50
Description and Design of Proposed Facility

3-34

1 Bardet, J.-P., N. Mace, and T. Tobita. “Liquefaction-Induced Ground Deformation and Failure.” 

2 Report to PEER/PG&E. Pasadena, California: Department of Civil Engineering, University of 

3 Southern California. 1999.

4

5 Bromhead, E.N. The Stability of Slopes. London, England: Blackies Academic & Professional. 

6 1992.

7

8 Bureau of Reclamation. “Earth Manual.” Part 1. Denver, Colorado: U.S. Department of the 

9 Interior. 1998.

10

11 Cetin, K.O., R.B. Seed, A.D. Kiureghian, K. Tokimatsu, L.F. Hardet, Jr., R.E. Kayen, and 

12 R.E.S. Moss. “Standard Penetration Test-Based Probabilistic and Deterministic Assessment of 

13 Seismic Soil Liquefaction Potential.” Journal of Geotechnical and Geoenvironmental 

14 Engineering. Vol. 130, No. 12. pp. 1,314–1,340. December 2004.

15

16 Cetin, K.O., A.D. Kiureghian, and R.B. Seed. “Probabilistic Models for the Initiation of Seismic 

17 Soil Liquefaction.” Structural Safety. Vol. 24. pp. 67–82. 2002.

18

19 Cetin, K.O., R.B. Seed, A.D. Kiureghian, K. Tokimatsu, L.F. Harder, Jr., R.E. Kayen, and 

20 I.M. Idriss. “SPT-Based Probabilistic and Deterministic Assessment of Seismic Soil Liquefaction 

21 Initiation Hazard.” PEER–2000/05. Pacific Earthquake Engineering Research Report. 

22 San Francisco, California: Pacific Gas and Electric Company. 2000.

23

24 Chowdhury, R. Geotechnical Slope Analysis. Leiden, The Netherlands: CRC Press/Balkema. 

25 2010.

26

27 Deatherage, J.D., J.R. Fahy, and L.W. Hansen. “Shear Testing of Geomembrane Soil 

28 Interfaces.” Chapter 8, Introduction to Evaluation, Design and Operation of Precious Metal 

29 Heap Leaching Projects. D. van Zyl, I. Hutchinson, and J. Kiel, eds. Littleton, Colorado: Society 

30 of Mining Engineers, Inc. pp. 45–50. January 1988.

31

32 Denson, R.H., R.D. Bennett, R.M. Wamsley, D.L. Bean, and D.L. Ainsworth.

33 NUREG/CR–5041, “Recommendations to the NRC for Review Criteria for Alternative Methods 

34 of Low-Level Radioactive Waste Disposal.” Washington, DC: NRC. 1987.

35

36 Department of the Navy. “Soil Dynamics, Deep Stabilization, and Special Geotechnical 

37 Construction.” NAVFAC DM 7.3. Alexandria, Virginia: Naval Facilities Engineering Command. 

38 1997. 

39

40 –––––. “Soil Mechanics.” NAVFAC DM 7.1. Alexandria, Virginia: Naval Facilities Engineering 

41 Command. 1986a.

42

43 –––––. “Foundations and Earth Structures.” NAVFAC DM 7.2. Alexandria, Virginia: Naval 

44 Facilities Engineering Command. 1986b.Ferritto, J.M. “Seismic Design Criteria for Soil 

45 Liquefaction.” Technical Report TR–2077-SHR. Port Hueneme, California: Naval Facilities 

46 Engineering Service Center. 1997.

47

48 Gilbert, R.B., F. Fernandez, and D.W. Horsfield. “Shear Strength of Reinforced Geosynthetic 

49 Clay Liner.” Journal of Geotechnical Engineering. Vol. 122, No. 4. April 1996.

50
Description and Design of Proposed Facility

3-35

Goodman, R.E. Introduction to Rock Mechanics. 2nd 1 edition. New York City, New York: 

2 John Wiley & Sons. 1989.

3

4 Goodman, R.E. and H.B. Seed. “Earthquake-Induced Displacements in Sand Embankments.” 

5 ASCE Journal of the Soil Mechanics and Foundations Division. Vol. 92, No. SM2. March 1966.

6

7 Hassan, A.M. and T.F. Wolff. “Search Algorithm for Minimum Reliability Index of Earth Slopes.” 

8 ASCE Journal of Geotechnical and Geoenvironmental Engineering. Vol. 125, No. 4.

9 pp. 301–308. April 1999.

10

11 Hynes, M.E. NUREG/CR–6622, “Probabilistic Liquefaction Analysis.” Washington, DC: NRC. 

12 November 1999.

13

14 Idriss, I.M. and R.W. Boulanger. “Semi-Empirical Procedures for Evaluating Liquefaction 

Potential During Earthquakes.” Proceedings of the Joint 11th 15 International Conference on Soil 

Dynamics & Earthquake Engineering and 3rd 16 International Conference on Earthquake 

17 Geotechnical Engineering. Berkeley, California: University of California. 2004.

18

19 Ishihara, K. and M. Yoshimine. “Evaluation of Settlements in Sand Deposits Following 

20 Liquefaction During Earthquake.” Soil Foundations. Vol. 32, No. 1. Japanese Society of Soil 

21 Mechanics and Foundation Engineering. 1990.

22

23 JBR Environmental Consultants, Inc. “Design and Construction Guidance Document for 

24 Precious Metals Heap Leach Extraction Facilities.” Salt Lake City, Utah: Utah Department of 

25 Environmental Quality. 1998.

26

27 Johnson, H.V., S.J. Spigolon, and R.J. Lutton. NUREG/CR–3356, “Geotechnical Quality 

28 Control: Low–Level Radioactive Waste and Uranium Mill Tailings Disposal Facilities.” 

29 Washington, DC: NRC. 1983.

30

31 Juang, C.H., S.Y. Fang, and E.H. Khor. “First-Order Reliability Method for Probabilistic 

32 Liquefaction Triggering Analysis Using CPT.” Journal of Geotechnical and Geoenvironmental 

33 Engineering. Vol. 132, No. 3. March 2006.

34

35 Koester, J.P., M.K. Sharp, and M.E. Hynes. NUREG/CR–5741, “Technical Bases for 

36 Regulatory Guide for Soil Liquefaction.” Washington, DC: NRC. 2000.

37

38 Lambe, T.W. and R.V. Whitman. Soil Mechanics, SI Version. New York City, New York: 

39 John Wiley & Sons. 1979.

40

41 Lupo, J.F. and K.F. Morrison. “Geosynthetic Design and Construction Approaches in the Mining 

42 Industry.” Geotextiles and Geomembranes. Vol. 25, No. 2. 2007.

43

44 Mejia, L.H. and H.B. Seed. “Comparison of 2-D and 3-D Dynamic Analysis of Earth Dams.” 

45 Journal of Geotechnical Engineering. Vol. 109, No. 11. November 1983.

46

47 Moss, R.E.S., R.B. Seed, R.E. Kayen, J.P. Stewart, A.D. Kiureghian, and K.O. Cetin. 

48 “CPT-Based Probabilistic and Deterministic Assessment of In Situ Seismic Soil Liquefaction 

49 Potential.” Journal of Geotechnical and Geoenvironmental Engineering. Vol. 132, No. 8. 

50 pp. 1,032–1,051. August 2006.

51
Description and Design of Proposed Facility

3-36

1 Muhtadi, O.A. “Heap Construction and Solution Application.” Chapter 6, Introduction to 

2 Evaluation, Design and Operation of Precious Metal Heap Leaching Projects. D. van Zyl, 

3 I. Hutchinson, and J. Kiel, eds. Littleton, Colorado: Society of Mining Engineers, Inc.

4 pp. 92–106. January 1988.

5

6 National Center for Earthquake Engineering Research. “Proceedings of the NCEER Workshop 

7 on Evaluation of Liquefaction Resistance of Soils.” T.L. Youd and I.M. Idriss, eds. Technical 

8 Report No. NCEER 97-002. Buffalo, New York: State University of New York. 1997.

9

10 Nelson, J.D., R.E. Wardwell, S.R. Abt, and W.P. Staub. NUREG/CR–3204, “Consolidation of 

11 Tailings.” Washington, DC: NRC. October 1983a.

12

13 Nelson, J.D., R.L. Volpe, R.E. Wardwell, S.A. Schumm, and W.P. Staub. NUREG/CR–3397, 

14 “Design Considerations for Long-Term Stabilization of Uranium Mill Tailings Impoundments.” 

15 Washington, DC: NRC. September 1983b.

16

17 Newmark, N.M. “Effects of Earthquakes on Dams and Embankments.” Geotechnique. 

18 June 1965.

19

20 NRC. NUREG/CP–0195. “Proceedings of the Workshop on Engineered Barrier Performance 

21 Related to Low-Level Radioactive Waste, Decommissioning, and Uranium Mill Tailings 

22 Facilities.” Washington, DC: NRC. Office of Nuclear Regulatory Research. August 2011.

23

24 –––––. Regulatory Guide 3.11, “Design, Construction, and Inspection of Embankment 

25 Retention Systems for Uranium Mills.” Rev. 3. Washington, DC: NRC, Office of Standards 

26 Development. Rev. 3. November 2008.

27

28 –––––. Regulatory Guide 1.132, “Site Investigations for Foundations of Nuclear Power Plants.” 

29 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. October 2003a.

30

31 –––––. Regulatory Guide 1.138, “Laboratory Investigations of Soils for Engineering Analysis 

32 and Design of Nuclear Power Plants.” Rev. 2. Washington, DC: NRC, Office of Nuclear 

33 Regulatory Research. December 2003b.

34

35 –––––. Regulatory Guide 1.198, “Procedures and Criteria for Assessing Seismic Soil 

36 Liquefaction at Nuclear Power Plant Sites.” Washington, DC: NRC. Office of Nuclear 

37 Regulatory Research. November 2003c.

38

39 –––––. NUREG–1623. “Design of Erosion Protection for Long-Term Stabilization.” Washington, 

40 DC: NRC. Office of Nuclear Material Safety and Safeguards. September 2002.

41

42 Seed, H.B. “Slope Stability During Earthquakes.” ASCE Journal of the Soil Mechanics and 

43 Foundations Division. Vol. 93, No. SM4. 1967.

44

45 Seed R.B. and R. Bonaparte. “Seismic Analysis and Design of Lined Waste Fills: Current 

46 Practice. Stability and Performance of Slopes and Embankments—II, Volume 1.” Proceedings 

47 of a Specialty Conference. R.B. Seed and R.W. Boulanger, eds. Geotechnical Special 

48 Publication No. 31. New York City, New York: American Society of Civil Engineers. 1992.

49
Description and Design of Proposed Facility

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1 Seed, R.B. and L.F. Harder. “SPT-Based Analysis of Cyclic Pore Pressure Generation and 

2 Undrained Residual Strength.” Proceedings of the H. Bolton Seed Memorial Symposium. 

3 Berkeley, California, May 10–11, 1990. Berkeley, California: University of California.

4 pp. 351–376. 1990.

5

6 Seed, H.B. and I.M. Idriss. “Ground Motions and Soil Liquefaction During Earthquakes.” 

7 Engineering Monograph: 5. Oakland, California: Earthquake Engineering Research Institute. 

8 1982.

9

10 –––––. “A Simplified Procedure for Evaluating Soil Liquefaction Potential.” Journal of Soil 

11 Mechanics and Foundation Division. Vol. 97, No. SM9. pp. 1,249–1,274. 1971. 

12

13 Seed, R.B., K.O. Cetin, R.E.S. Moss, A.M. Kammerer, J. Wu, J.M. Pestana, M.F. Riemer, 

14 R.B. Sancio, J.D. Bray, R.E. Kayen, and A. Faris. “Recent Advances in Soil Liquefaction 

Engineering: A Unified and Consistent Framework.” 26th 15 Annual ASCE Los Angeles 

16 Geotechnical Spring Seminar, Long Beach, California, April 2003. Berkeley, California: 

17 University of California. 2003.

18

19 Seed, H.B., R.T. Wong, I.M. Idriss, and K. Tokimatsu. “Moduli and Damping Factors for 

20 Dynamic Analyses of Cohesionless Soils.” Journal of Geotechnical Engineering. Vol. 112, 

21 No. 11. pp. 1,016–1,032. November 1986.

22

23 Strachan, C. and R. Dorey. “Geotechnical Studies.” Chapter 10, Introduction to Evaluation, 

24 Design and Operation of Precious Metal Heap Leaching Projects. D. van Zyl, I. Hutchinson, 

25 and J. Kiel, eds. Littleton, Colorado: Society of Mining Engineers, Inc. pp. 152–175. 

26 January 1988.

27

28 Thiel, R. and M.E. Smith. “State of the Practice Review of Heap Leach Pad Design Issues.” 

29 Geotextiles and Geomembranes. Vol. 22, No. 6. pp. 555–568. December 2004.

30

31 Transportation Research Board. “Seismic Analysis and Design of Retaining Walls, Buried 

32 Structures, Slopes, and Embankments.” NCHRP Report 611. Washington, DC: Federal 

33 Highway Administration, National Cooperative Highway Research Program. 2008.

34

35 Ulrich, B., A. Andrade, and T. Gardner. “Lessons Learnt from Heap Leaching Operations in 

36 South America-An Update.” The Journal of the South African Institute of Mining and Metallurgy. 

37 January/February 2003.

38

39 U.S. Army Corps of Engineers. “Division 31–Earthwork.” Unified Facilities Guide Specification 

40 UFGS–31. Washington, DC: Department of the Army. 2008.

41

42 –––––. “Reliability Analysis and Risk Assessment for Seepage and Slope Stability Failure 

43 Modes for Embankment Dams.” Engineering Manual ETL1110–2–561, Washington, DC: 

44 Department of the Army, Office of the Chief of Engineers. January 2006. 

45

46 –––––. “General Design and Construction Considerations for Earth and Rock-Fill Dams.” 

47 Engineering Manual EM1110-2-2300, Department of the Army, Office of the Chief of Engineers. 

48 July 2004. 

49

50 –––––. “Slope Stability.” EM1110–2–1902. Washington, DC: Department of the Army.

51 October 2003.
Description and Design of Proposed Facility

3-38

1 –––––. “Geotechnical Investigations.” Engineering Manual EM1110–1–1804. Washington, DC: 

2 Department of the Army, Office of the Chief of Engineers. January 2001.

3

4 –––––. “Earthquake Design and Analysis for Corps of Engineer Dams.” ER1110–2–1806. 

5 Washington, DC: Department of the Army, Office of the Chief of Engineers. July 1995a.

6

7 –––––. “Construction Control of Earth and Rock-Fill Dams.” Engineering

8 Manual EM1110–2–1911. Washington, DC: Department of the Army, Office of the Chief of 

9 Engineers. September 1995b.

10

11 –––––. “Instrumentation of Embankment Dams and Levees.” Engineering

12 Manual EM1110–2–1908. Washington, DC: Department of the Army, Office of the Chief of 

13 Engineers. June 1995c.

14

15 –––––. “Settlement Analysis.” Engineering Manual EM1110–1–1904. Washington, DC: 

16 Department of the Army, Office of the Chief of Engineers. September 1990.

17

18 –––––. “Laboratory Soils Testing.” EM1110–2–1906. Washington, DC: Department of Army, 

19 Office of the Chief Engineers. August 1986. 

20

21 U.S. Department of Agriculture. “Construction Specification 254–Earthfill.” Washington, DC: 

22 Natural Resources Conservation Service. 2008.

23

24 –––––. “Gradation Design of Sand and Gravel Filters.” Part 633, National Engineering 

25 Handbook. Chapter 26. Washington, DC: U.S. Department of Agriculture. 1994.

26

27 U.S. Federal Emergency Management Agency. “Federal Guidelines for Dam Safety: Glossary 

28 of Terms.” Washington, DC: U.S. Department of Homeland Security. 2004.

29 –––––. “Federal Guidelines for Dam Safety: Emergency Action Planning for Dam Owners.” 

30 Washington, DC: U.S. Federal Emergency Management Agency. 1998.

31

32 Van Zyl, D.J.A., I.P.G. Hutchison, and J.E. Kiel. “Introduction to Evaluation, Design and 

33 Operation of Precious Metal Heap Leaching Projects.” Littleton, Colorado: Society of Mining 

34 Engineers. 1988.

35

36 Walters, W.H. NUREG/CR–2684, “Rock Riprap Design Methods and Their Applicability to 

37 Long–Term Protection of Uranium Mill Tailings Impoundments.” Washington, DC: NRC. 1982.

38

39 Wu, T.H. “Reliability Analysis of Slopes.” Chapter 11, Reliability-Based Design in Geotechnical 

40 Engineering: Computations and Applications. K.K. Phoon, ed. New York City, New York: 

41 Taylor and Francis. 2008.

42

43 Youd, T.L., I.M. Idriss, R.D. Andrus, I. Arango, G. Castro, J.T. Christian, R. Dobry, W.D.L. Finn, 

44 L.F. Harder, Jr., M.W. Hynes, K. Ishihara, J.P. Koester, S.S.C. Liao, W.F. Marcuson III, 

45 G.R. Martin, J.K. Mitchell, Y. Moriwaki, M.S. Power, P.K. Robertson, R.B. Seed, and 

46 K.H. Stokoe II. “Liquefaction Resistance of Soils: Summary Report from the 1996 NCEER and 

47 1998 NCEER/NSF Workshops on Evaluation of Liquefaction Resistance of Soils.” Journal of 

48 Geotechnical and Geoenvironmental Engineering. Vol. 127, No. 10. October 2001.

49

50
Description and Design of Proposed Facility

3-39

1 3.4 Uranium Recovery Process 

2

3 3.4.1 Areas of Review 

4

5 The staff should review the physical descriptions and operating characteristics for the major 

6 equipment of the recovery cycle. The staff should also review descriptions of the proposed 

7 process information and controls, as well as radiation sampling and monitoring equipment. 

8 Controls mean the apparatus or mechanisms that could affect the chemical, physical, 

9 metallurgical, or nuclear processes of the facility in such a manner as to influence radiation 

10 health and safety. The staff should review a diagram that indicates the plant layout and 

11 locations where dusts, fumes, or gases would be generated; locations of all ventilation, filtration, 

12 confinement, and dust collection systems; and radiation safety and radiation monitoring devices.

13

14 In addition, staff should review the list and specifications related to all radioactive and 

15 hazardous materials used in the recovery plant and chemical storage facilities. These should 

16 be reviewed for the hazards associated with the quantities, locations, operating flow rates, 

17 temperatures, and pressures of these materials.

18

19 While safety concerns with the use of all hazardous materials are important and need to be 

20 addressed, direct NRC regulatory authority is limited to situations where hazardous materials 

21 have a potential effect on radiological health and safety. Chemicals of concern typically used in 

22 uranium recovery facilities are identified in NUREG/CR–6733 (NRC, 2001) and DOE/EIA–0592

23 (DOE, 1995). Therefore, staff should review the list of applicable federal, state, and local 

24 regulations that the applicant intends to use to determine that all hazardous chemicals that have 

25 the potential to impact radiological health and safety are safely handled. Staff should also 

26 review the safety features used in the facility process design for eliminating or mitigating the 

27 hazards these materials present.

28

29 3.4.2 Review Procedures 

30

31 The staff should use the following procedures when conducting the review of the description of 

32 the uranium recovery process:

33

34 (1) Ensure that the ore operations are adequately described, including crushing, 

35 pulping, and dissolution. This information should meet, in part, the requirements of 

36 10 CFR 40.32(c) and (d).

37

38 (2) Verify that the proposed plant material balances and flow rates are adequately 

39 described. Ensure that the plans, specifications, inspection programs, and construction 

40 quality assurance/quality control programs are adequate to meet, in part, the 

41 requirements of 10 CFR 40.32(c) and (d).

42

43 (3) Verify that the applicant has identified the volume of the largest tank within the building 

44 and that the volume of the tank can be contained within the building. Additionally, verify 

45 that the applicant has identified measures taken to minimize potential for leakage 

46 through the floor. Verify that the applicant has adequately described protection pipes 

47 running to and from buildings or chemical storage areas. This information should meet, 

48 in part, the requirements of 10 CFR 40.32(c) and (d). 

49
Description and Design of Proposed Facility

3-40

1 (4) Verify that all radiation protection aspects of the plant design, including ventilation, 

2 filtration, confinement, dust collection, and radiation monitoring equipment are adequate 

3 to meet, in part, the requirements of 10 CFR 40.32(c) and 10 CFR Part 40, Appendix A, 

4 Criterion 8.

5

6 (5) Determine that operating parameters are provided and are adequate to meet, in part, the 

7 requirements of 10 CFR 40.32(c).

8

9 For facility instrumentation

10

11 (5) Verify that instrumentation has been described for the various components of the 

12 processing facility and the production circuit. This information should meet, in part, the 

13 requirements of 10 CFR 40.32(c).

14

15 3.4.3 Acceptance Criteria

16

17 The description of the uranium recovery process is acceptable if it meets the following criteria: 

18

19 (1) The description of the recovery process includes proposed plant material balances and 

20 flow rates that are adequately described. The amount of flow into the plant has been 

21 shown to equal the sum of the various flows out of the plant.

22

23 (2) Plans, specifications, and inspection programs are adequate to construct the facility 

24 according to accepted engineering practices. The applicant provides detailed 

25 information on processing equipment (e.g., tanks, ion exchange columns, piping 

26 materials). A commitment to adhere to local building codes during facility construction is 

27 provided. Construction quality assurance/quality control programs exist for radiologically 

28 significant structures, including:

29

30 (a) Processing plant sumps, berms, containment, and pump pits;

31 (b) Piping;

32 (c) Processing plant structures; and

33 (d) Tornado, hurricane, earthquake, and fire protection, as necessary.

34

35 (3) The processing building has been designed to contain the volume of the largest tank 

36 without a release to the environment. This could be through the use of a sump, or a 

37 concrete berm around the tank. The applicant has also identified measures to prevent 

38 liquid flow through cracks or joints in the floor of the process building. The applicant has 

39 proposed leak detection or secondary containment for pipes running to and from 

40 buildings or chemical storage areas. 

41

42 (3) All ventilation, filtration, confinement, dust collection, and radiation monitoring equipment 

43 are described as to size, type, and location. Availability requirements for safety 

44 equipment are adequately stated, and measures for ensuring availability and reliability 

45 are clearly identified, including the type of safety equipment, its locations, the 

46 maintenance requirements, and the responsibility for performing maintenance.

47

48 (4) Specifications, quantities, locations, and operating conditions, such as flow rates, 

49 temperatures, and pressures of radioactive materials and those hazardous materials 

50 with the potential to impact radiological safety, are clearly identified together with the 

51 hazards associated with these materials. Furthermore, controls used for eliminating or 
Description and Design of Proposed Facility

3-41

1 mitigating the hazards presented by the radioactive materials and those hazardous 

2 materials with the potential to impact radiological safety are adequately described.

3

4 The description of the facility instrumentation is acceptable if it meets the following criteria:

5

6 (5) Instrumentation has been described for the various components of the processing facility 

7 and the production circuit. Specific brands of instrumentation are not necessary;

8 however, the basic type of instrument or component that is used to maintain control of 

9 radioactive and 11e.(2) byproduct material is provided. Instrumentation is designed to 

10 allow the plant operator to continuously monitor and control a variety of systems and 

11 parameters, including total flow into the plant, total waste flow leaving the plant, tank 

12 levels, and the yellowcake dryer. Furthermore, the instrumentation includes alarms and 

13 interlocks in the event of a failure.

14

15 Control components of the systems are equipped with backup systems that activate in 

16 the event of a failure of the operating system or a common cause failure, such as a fire.

17

18 Manufacturer’s recommendations for maintenance and operation of yellowcake dryers, 

19 and checking and logging requirements contained in 10 CFR Part 40, Appendix A, 

20 Criterion 8, are followed.

21

22 3.4.4 Evaluation Findings

23 If the staff determines that no license conditions are required for the description of the uranium 

24 recovery process because the applicant or licensee provided adequate and complete 

25 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

26 is needed for the evaluation findings section. Begin the section with the sentence: “NRC staff 

27 has completed its review of the description of the uranium recovery process at the conventional 

28 uranium mill or heap leach facility in accordance with Section 3.4.3 of the standard review plan.” 

29 Following this sentence, state what information the applicant provided in the application. As 

30 discussed in the introduction of this SRP, a bullet or sentence format may be used to list what

31 information the applicant has provided. 

32

33 After the description of the information the applicant provided, the following or a similar 

34 statement can be added: “Based on the review conducted by NRC staff, the information 

35 provided in the application meets the applicable acceptance criteria of Section 3.4.3 of the 

36 standard review plan. Therefore, NRC staff concludes that the applicant’s description of the 

37 uranium recovery process at the conventional uranium mill or heap leach facility is acceptable 

38 and is in compliance with 10 CFR 40.32(c), which requires the applicant’s proposed equipment, 

39 facilities, and procedures to be adequate to protect health and minimize danger to life or 

40 property; 10 CFR 40.32(d), which requires that the issuance of a license will not be inimical to 

41 the health and safety of the public; and 10 CFR Part 40, Appendix A, Criterion 8, which provides 

42 requirements for control of airborne effluent releases.” As a concluding statement, indicate the 

43 reason why the applicant’s information is considered adequate and complete, and why or how 

44 that information complies with the identified regulatory requirements.

45

46 If license conditions are needed, then a more detailed discussion is typically required. Begin 

47 this section with the sentence: “NRC staff has completed its review of the description of the 

48 uranium recovery process at the conventional uranium mill or heap leach facility in accordance 

49 with Section 3.4.3 of the standard review plan.” Following this sentence, state what information 
Description and Design of Proposed Facility

3-42

1 the applicant provided in the application, including identification of the information that was 

2 omitted or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format 

3 may be used to list what information the applicant has provided. Next, state why a license 

4 condition is needed, followed by the license condition or conditions. 

5

6 In a separate paragraph following the discussion of the required license condition(s), include the 

7 statement: “Based on the review conducted by NRC staff, the information provided in the 

8 application, supplemented by provisions of the license condition(s) discussed above, meets the 

9 applicable acceptance criteria of Section 3.4.3 of the standard review plan. Therefore, NRC 

10 staff concludes that the applicant’s description of the uranium recovery process at the 

11 conventional uranium mill or heap leach facility is acceptable and is in compliance with

12 10 CFR 40.32(c), which requires the applicant’s proposed equipment, facilities, and procedures 

13 to be adequate to protect health and minimize danger to life or property; 10 CFR 40.32(d), 

14 which requires that the issuance of a license will not be inimical to the health and safety of the 

15 public; and 10 CFR Part 40, Appendix A, Criterion 8, which provides requirements for control of 

16 airborne effluent releases.” If not discussed in the preceding paragraph(s), include a statement

17 or summation as to why or how the application and license condition(s) jointly comply with the 

18 identified regulatory requirements.

19

20 3.4.5 References

21

22 DOE. “Decommissioning of U.S. Uranium Production Facilities.” DOE/EIA–0592. Washington, 

23 DC: DOE, Office of Coal, Nuclear, Electric and Alternate Fuels. 1995.

24

25 NRC. NUREG/CR–6733, “A Baseline Risk-Informed, Performance-Based Approach for In-Situ

26 Leach Uranium Extraction Licensees.” Washington, DC: NRC. 2001. 

27

28 3.5 Waste Management

29

30 3.5.1 Areas of Review

31

32 This section focuses on the requirements to manage wastes; wastes include liquid (process 

33 effluents), gaseous effluents, and solid wastes, including both byproduct material and 

34 non-byproduct material. Areas of review should include:

35

36 (1) Quantities and compositions of wastes expected during construction, operation,

37 and decommissioning;

38

39 (2) Effluent control systems for liquids and gases;

40

41 (3) Control of solid and liquid wastes; and

42

43 (4) Design specifications of any waste retention and disposal systems such as surface

44 impoundments and deep injection wells.

45

46
Description and Design of Proposed Facility

3-43

1 3.5.2 Review Procedures

2

3 The staff should use the following procedures when conducting the review of 

4 waste management:

5

6 (1) Determine that the description of the proposed conventional uranium mill or heap leach 

7 process is adequate for the type and quantity of wastes generated, including a 

8 description of the chemical and radioactive characteristics of waste solutions. The 

9 description should include: (a) an analysis and evaluation on the nature of the 

10 environment; (b) the location of other potentially affected licensed and unlicensed 

11 facilities; and (c) analyses and procedures to ensure that doses are maintained as low 

12 as is reasonably achievable (ALARA) and within the dose limits in 10 CFR Part 20. This 

13 information should meet, in part, the requirements of 10 CFR 20.2002; 10 CFR 20.2007;

14 10 CFR Part 40, Appendix A, Criteria 5G(1) and 8.

15

16 (2) Verify that monitoring and control systems for the facility are located to optimize their 

17 intended function and are appropriate for the types of effluents generated. This 

18 information should meet, in part, the requirements of 10 CFR 20.1101; 10 CFR 20.1301; 

19 10 CFR Part 20, Appendix B, Table 2; 10 CFR 40.32(c); 10 CFR 40.41(c); 10 CFR Part 

20 40, Appendix A, Criteria 7 and 8; and 40 CFR Part 190.

21

22 (3) Review the application to determine that the effluent control systems will limit 

23 exposures under both normal and accident conditions. Ensure that the application 

24 also provides information on the health and safety impacts of system failures and 

25 identifies contingencies for such occurrences. In addition, verify that the application 

26 describes minimum performance specifications for the operation of the effluent 

27 controls and the frequencies of tests and inspections to ensure proper performance 

28 to specifications. This information should meet, in part, the requirements of 

29 10 CFR 40.32(c) and 10 CFR Part 40, Appendix A, Criteria 7 and 10.

30

31 (4) Review the application to determine that it addresses contaminated solid waste 

32 management and disposal. This information should meet, in part, the requirements of 

33 10 CFR Part 20, Subpart C; 10 CFR 40.31(h); and 10 CFR Part 40, Appendix A, 

34 Criterion 2.

35

36 The staff should use the following procedures when reviewing the liquid effluent 

37 control systems:

38

39 (5) Review the description of instrumentation for the liquid effluent disposal method 

40 considered to determine that it has been adequately described. The review should focus 

41 on instrumentation used to measure flow rates and pressures. Review the methods for 

42 controlling liquid effluents, including the use of neutralizing agents to immobilize 

43 hazardous constituents. This information should meet, in part, the requirements of 

44 10 CFR 20.1301; 10 CFR 20.1302; 10 CFR 20.2002; 10 CFR 20.2007; 10 CFR 40.32(c);

45 10 CFR 40.41(c); 10 CFR Part 40, Appendix A, Criteria 5E(1), 5E(4), 7, and 7A; and 

46 40 CFR Part 190.

47

48 (6) If surface impoundments are considered as a method to dispose of liquid effluents, 

49 review the proposed design of surface impoundments, the monitoring and inspection 

50 program, and the corrective action plans to confirm that they are adequately designed to 
Description and Design of Proposed Facility

3-44

1 prevent migration of waste from the surface impoundments to the subsurface soil, 

2 groundwater, or surface water (Section 3.3 of this SRP).

3

4 (7) Confirm that water quality certification and discharge permits have been obtained

5 or plans are in place to obtain them in accordance with 10 CFR 20.2007 and 

6 40 CFR Part 146. Determine that releases of process waste water to surface waters 

7 comply with 40 CFR 440.34 and 10 CFR 20.1302(b). Verify that release of liquids into 

8 surface waters complies with the public dose limits in 10 CFR 20.1301; the water 

9 concentration limits defined in 10 CFR Part 20, Appendix B; and 40 CFR Part 190.

10

11 The staff should use the following procedures when reviewing the gaseous and airborne 

12 particulate effluent control systems: 

13

14 (8) Verify that areas where dusts, fumes, or gases would be generated are clearly identified, 

15 along with a description of the source of the emissions. This information should meet, in 

16 part, the requirements of 10 CFR 40.41(c).

17

18 (9) Review the application to confirm it demonstrates that adequate ventilation systems are 

19 planned for process buildings to avoid gaseous and radioactive particulate emission 

20 buildup, including radon gas, and that ventilation systems are consistent with the 

21 requirements of Regulatory Guide 8.31, “Information Relevant to Ensuring that 

22 Occupational Radiation Exposures at Uranium Mills Will Be As Low As Reasonably 

23 Achievable,” Revision 1 (NRC, 2002, Section 3.3). The ventilation system and controls 

24 should be sufficient to maintain airborne concentrations of radon and its progeny in the 

25 workplace to less than 25% of the Derived Air Concentration (DAC) given in Table 1 of 

26 10 CFR Part 20, Appendix B, as recommended in Regulatory Guide 8.31. According to 

27 the regulatory guide, the 25 percent figure is used to encourage the use of ventilation

28 systems and controls in an effort to prevent the existence of airborne radioactivity areas. 

29 This information should meet, in part, the requirements of 10 CFR 20.1701; 10 CFR Part 

30 20, Appendix B; 10 CFR 40.32(c); 10 CFR 40.41(c); and 10 CFR Part 40, Appendix A, 

31 Criteria 7 and 8.

32

33 (10) Verify that the application demonstrates that the operations will be conducted so 

34 that airborne effluent releases are ALARA. This information should meet, in part, the 

35 requirements of 10 CFR 20.1101 and 10 CFR Part 40, Appendix A, Criterion 8.

36

37 (11) Confirm that gaseous and particulate emissions within enclosed buildings are properly 

38 controlled. This information should meet, in part, the requirements of 10 CFR Part 40, 

39 Appendix A, Criterion 8.

40

41 (12) Determine that emissions from yellowcake drying operations are properly controlled. 

42 This information should meet, in part, the requirements of 10 CFR Part 40, Appendix A, 

43 Criterion 8.

44

45 3.5.3 Acceptance Criteria

46

47 The description of waste management is acceptable if it meets the following criteria: 

48

49 (1) The description of the conventional uranium mill or heap leach process identifies 

50 gaseous and liquid effluents, and solid wastes that will be generated. Physical, 

51 chemical, and radiological characteristics of each waste type are identified, and a 
Description and Design of Proposed Facility

3-45

1 determination that a waste is or is not byproduct material is provided. In addition, the 

2 quantity of each waste type and its retention and transport potential (e.g., sorptive 

3 and reactive characteristics with the host media) are identified, as well as the manner 

4 of disposal.

5

6 (2) Monitoring and control systems for the facility are located to optimize their intended 

7 function and are appropriate for the types of effluents generated. The intended 

8 purposes of measurement devices are clearly stated, and criteria for monitoring are 

9 provided. Preoperational monitoring and detection monitoring programs are developed 

10 for chemical and radiological constituents to be monitored on a site-specific basis. 

11 Monitors used to assess worker exposures are placed in locations of maximum 

12 anticipated radionuclide concentration based on determination of airflow patterns. 

13 Milling operations are conducted under the condition that airborne effluents releases are 

14 maintained ALARA. Control and monitoring systems at the proposed facility protect 

15 health and minimize danger to life and property.

16

17 (3) The application demonstrates that the effluent control systems will limit exposures under 

18 both normal and accident conditions. The type of effluent controls are described, 

19 including the specific equipment to be used, parameters used to measure performance, 

20 and frequency of performance assessments. The application also provides information 

21 on the health and safety impacts of system failures and identifies contingencies for 

22 such occurrences.

23

24 The application describes minimum performance specifications for the operation of the 

25 effluent controls and the frequencies of tests and inspections to ensure proper 

26 performance with specifications. Details of acceptable leakage and spill control 

27 techniques are found in Section 4.1 of this SRP. Acceptable methods for testing, 

28 maintenance, and inspection of effluent controls are consistent with Regulatory 

29 Guide 3.56, “General Guidance for Designing, Testing, Operating, and Maintaining 

30 Emission Control Devices at Uranium Mills” (NRC, 1986, Section 1). The application 

31 provides sufficient information on how the effluent control and detection monitoring 

32 program at the proposed facility will provide sufficient data and information for NRC to 

33 establish standards, if leakage of hazardous constituents from surface impoundments 

34 is detected.

35

36 (4) The application identifies and differentiates solid byproduct material (e.g., contaminated 

37 soil and debris by process solutions, pipes, building materials, filters, protective clothes), 

38 contaminated solid waste that is not byproduct material (e.g., used equipments, sanitary 

39 waste), and hazardous solid waste (e.g., waste oil, used batteries). The application 

40 contains a description of the methods to be used for disposing of each solid waste type

41 that is generated during operation of the facility. The storage of byproduct material that 

42 either cannot or will not be decontaminated and released for unrestricted use will be 

43 managed to ensure compliance with occupational dose limits in 10 CFR Part 20, 

44 Subpart C. The application provides an estimate of the amount of contaminated 

45 material that will be generated and disposal method identified. In particular, the 

46 application describes whether contaminated equipments are to be disposed into 

47 surface impoundments, or stored on site, or shipped to an offsite disposal facility at 

48 a later date.

49

50
Description and Design of Proposed Facility

3-46

1 For process effluent control systems:

2

3 (5) Liquid effluents generated during the uranium mill or heap leach process are designated 

4 as byproduct material. Acceptable control methods include diversion of liquid effluents 

5 to surface impoundments, land application sites, deep injection wells, or their 

6 combinations. To dispose of liquid waste in surface impoundments, the applicant 

7 provides (i) a description of physical properties and chemical toxicity of radioactive and 

8 nonradioactive constituents of liquid effluents that are important to risk, (ii) a description 

9 of design features of surface impoundments, (iii) the use of neutralizers to promote 

10 immobilization of hazardous constituents, and (iv) a description of onsite instrumentation 

11 and procedures for leakage detection and seepage control to ensure adequate 

12 containment of liquid effluent in surface impoundments. 

13

14 To dispose of liquid waste after treatment by onsite land application, the application 

15 provides (i) a description of the waste including its physical and chemical properties that 

16 are important to risk, (ii) a description of the proposed manner and conditions of waste 

17 disposal, and (iii) onsite instrumentations, analyses, and procedures to ensure that 

18 doses are maintained ALARA and within the dose limits of 10 CFR 20.1301. For land 

19 application, the application describes activities and onsite instrumentation in sufficient 

20 detail for assessing: (i) projected concentrations of radioactive contaminants in the soils 

21 and demonstrates that instrumentation and detection systems will be adequate to ensure 

22 that the concentration of radium and other radionuclides in the soil will not exceed the 

23 groundwater protection standards; (ii) projected impacts on groundwater and 

24 surface-water quality; (iii) projected impacts on land use, particularly crops, vegetation, 

25 and livestock grazing; and (iv) projected exposures and health risks that may be 

26 associated with radioactive constituents reaching the food chain. The specific toxicity 

27 evaluations and necessary permits are sufficient to conform to the applicable 

28 environmental and health protection regulations. In the absence of compliance 

29 monitoring wells in the uppermost aquifer beneath the proposed land application site, 

30 onsite instrumentation demonstrates that contaminants will not be returned to the 

31 groundwater and cause site-specific groundwater protection standards to be exceeded 

32 and will not adversely affect groundwater levels and site-hydrology beneath the 

33 proposed conventional uranium mill or heap leach facility. The application proposes 

34 periodic soil surveys that include contaminant monitoring to verify that contaminant 

35 levels in the soil do not exceed the projected levels. A remediation plan is in place to be 

36 implemented in the event that the projected levels are exceeded and also includes a 

37 remediation plan that can be implemented if projected levels are exceeded.

38

39 If the liquid effluent is to be treated and reinjected into a deep disposal well, the 

40 appropriate local, state, or federal authorities will approve the injection program. The 

41 licensee has committed to provide (i) a description of the chemical toxicity of radioactive 

42 and nonradioactive constituents of liquid effluents that are important to risk, (ii) a 

43 description of the proposed manner and conditions of waste disposal, (iii) an analysis 

44 and evaluation of pertinent information on the affected environment, (iv) information 

45 on the nature and location of other facilities likely to be affected, and (v) onsite

46 instrumentation in sufficient detail to demonstrate that liquid effluents disposed into a 

47 designated aquifer will not exceed the approved injection well capacity and have 

48 adequate monitoring well and instrumentation to ensure that groundwater protection 

49 standards in adjacent aquifers will not be exceeded, and that doses are ALARA and 

50 within dose limits for individual members of the public.

51
Description and Design of Proposed Facility

3-47

1 For release of liquid waste to surface waters, the applicant has committed to comply 

2 with dose limits and will have adequate sampling instruments and procedures to 

3 demonstrate that doses are maintained ALARA. NRC has no specific requirements for 

4 nonradiological constituents, and the applicant has committed to adopt the appropriate 

5 state limits. Anticipated discharges are described in enough detail to evaluate 

6 environmental impacts. The applicant has committed to comply with NRC requirements 

7 for decommissioning before facility closure and license termination. Decommissioning 

8 requirements are discussed in Section 7 of this SRP.

9

10 (6) If surface impoundments are considered as a method to dispose of liquid effluents, the 

11 proposed design of surface impoundments, the monitoring and inspection program and 

12 the corrective action plans are adequately designed to prevent migration of waste from 

13 the surface impoundments to the subsurface soil, groundwater, or surface water. The 

14 design, installation, and operation of surface impoundments at the proposed 

15 conventional uranium mill or heap leach site used to manage byproduct material are 

16 consistent with guidance provided in Regulatory Guide 3.11, Revision 3, (NRC, 2008,

17 Section 1). Onsite retention ponds are designed and operated in a manner that prevents 

18 migration of liquid waste from the all surface impoundments to the uppermost aquifer. 

19 The monitoring and inspection program consists of documented daily checks of 

20 freeboard of surface impoundments and the leak detection system. Section 3.3 of this 

21 SRP contains additional discussion of the design and evaluation of surface

22 impoundments, diversion facilities, and the monitoring and inspection program.

23

24 Corrective actions will commence on leak confirmation and will consist of transferring the 

25 solution to another surface impoundment so that liner repairs can be made. Thus, 

26 sufficient freeboard capacity will be maintained in the surface impoundments such that 

27 any one surface impoundment could be transferred to the remaining surface 

28 impoundments in the event of a leak. An additional freeboard requirement is that water 

29 levels will be kept far enough below the top of the retention pond to prevent waves from 

30 overtopping during high wind conditions. 

31

32 Actions to be taken in the event that surface impoundment water analyses 

33 indicate leakage include (i) notifying NRC by telephone within 48 hours of verification, 

34 (ii) analyzing standpipe water quality samples for leak parameters once every 7 days 

35 during the leak period and once every 7 days for at least 14 days following repairs, and 

36 (iii) filing a written report with NRC within 30 days of first notifying NRC that a leak exists. 

37 This report includes analytical data and describes the corrective actions and the results 

38 of those actions.

39

40 (7) The applicant has obtained applicable local, state, and federal permits for the disposal of 

41 any toxic or hazardous effluents and properties of materials. If deep disposal of liquid 

42 effluents is to be implemented, the applicant’s proposal satisfies U.S. Environmental 

43 Protection Agency (EPA) regulations for the underground injection control program, and 

44 applicants will obtain necessary permits from the EPA and states EPA authorizes to 

45 enforce these provisions. Applicants disposing of liquid waste from process water by 

46 injection in deep wells will comply with NRC regulatory provisions for decommissioning.

47

48

49
Description and Design of Proposed Facility

3-48

1 If the treated liquid effluents are to be released to surface waters, release of liquids into 

2 surface waters will comply with the public dose limits in 10 CFR 20.1301, which may be 

3 demonstrated by one of the following methods:

4

5 (a) The application demonstrates compliance with effluent concentration limits in 

6 10 CFR Part 20, Appendix B, by one of the following methods and shows that if 

7 an individual were continuously present in an unrestricted area, the dose from 

8 external sources would not exceed 0.02 mSv/hr [2 mrem/hr] or 0.5 mSv/yr 

9 [50 mrem/yr]:

10

11 (i) Showing that the discharge of effluent from any surface impoundment is 

12 within 10 CFR Part 20, Appendix B effluent concentration limits at the 

13 point of discharge.

14

15 (ii) Monitoring the incoming process water to demonstrate compliance with 

16 the effluent discharge limits in 10 CFR Part 20, Appendix B for 

17 process water.

18

19 (b) The application demonstrates that the total effective dose equivalent to the 

20 individual likely to receive the highest dose from the facility does not exceed the 

21 annual dose limit for the public. 

22

23 (c) The application demonstrates compliance with 40 CFR 440.34, which prohibits 

24 discharges of process waste water to navigable waters by conventional uranium 

25 mill and heap leach extraction operations.

26

27 For gaseous and airborne particulate effluent control systems:

28

29 (8) Areas where dusts, fumes, or gases would be generated are clearly identified, along with 

30 a description of the source of the emissions. The applicant identifies locations of specific 

31 release points including discharge points. An acceptable release point would be that 

32 defined in Regulatory Guide 1.21, “Measuring, Evaluating, and Reporting Radioactive 

33 Material in Liquid and Gaseous Effluents and Solid Waste,” Revision 2 (NRC, 2009). 

34 This definition states that a release point is:

35

36 A location from which radioactive materials are released from a system,

37 structure, or component (including evaporative releases and leaching from ponds 

38 lakes in the controlled or restricted area before release under 10 CFR 20.2001)

39

40 A discharge point is consistent with the definition in Regulatory Guide 1.21, Revision 2

41 (NRC, 2009). This definition states that a discharge point is”

42

43 A location from which radioactive material enters the unrestricted area—This 

44 would be the point beyond the vertical plane of the unrestricted area (surface 

45 or subsurface).

46

47 (9) The application demonstrates that adequate ventilation systems are planned for process 

48 buildings to avoid gaseous and airborne particulate emissions buildup, including radon 

49 gas. Proposed ventilation systems are consistent with the requirements of Regulatory 

50 Guide 8.31, Revision 1 (NRC, 2002, Section 3.3).

51
Description and Design of Proposed Facility

3-49

1 Ventilation systems emphasize (i) recovery solutions entering the plant, (ii) radon gas 

2 mobilization from the extraction process (where tanks are vented), and (iii) uranium 

3 particulate emissions resulting from drying and packaging operations and spills. Aspects 

4 of design that can significantly limit airborne releases may include closed production 

5 systems (i.e., no venting) and the use of vacuum dryers that eliminate airborne uranium 

6 particulate releases from drying operations.

7

8 (10) The application demonstrates that the operations will be conducted so that airborne 

9 effluent releases are ALARA.

10

11 (11) Airborne effluent emissions within enclosed buildings are properly controlled. Effective 

12 control of airborne effluent emissions is achieved by using a pressurized processing tank 

13 system that eliminates venting in process buildings or by using appropriate ventilation 

14 systems in buildings where airborne effluent emissions are expected. 

15

16 (12) Emissions from yellowcake drying operations are properly controlled. Acceptable control 

17 of yellowcake emissions from the dryer is achieved by meeting the criteria of Regulatory 

18 Guide 3.56 (NRC, 1986, Section 1).

19

20 3.5.4 Evaluation Findings

21

22 If the staff determines that no license conditions are required for waste management because 

23 the applicant or licensee provided adequate and complete information that fully addresses all 

24 relevant regulatory requirements, typically a single paragraph is needed for the evaluation 

25 findings section. Begin the section with the sentence: “NRC staff has completed its review of 

26 the description of waste management at the conventional uranium mill or heap leach facility in 

27 accordance with Section 3.5.3 of the standard review plan.” Following this sentence, state 

28 what information the applicant provided in the application. As discussed in the introduction 

29 of this SRP, a bullet or sentence format may be used to list what information the applicant 

30 has provided. 

31

32 After the description of the information the applicant provided, the following or a similar 

33 statement can be added: “Based on the review conducted by NRC staff, the information 

34 provided in the application meets the applicable acceptance criteria of Section 3.5.3 of the 

35 standard review plan. Therefore, NRC staff concludes that the applicant’s description of waste 

36 management at the conventional uranium mill or heap leach facility is acceptable and is in 

37 compliance with 10 CFR Part 20, Subpart C, which requires that occupational dose limits need

38 to be controlled; 10 CFR 20.1101, which requires that an acceptable radiation protection 

39 program that achieves ALARA goals is in place and that a constraint on air emissions, excluding 

40 Rn-222 and its decay products, will be established to limit doses from these emissions;

41 10 CFR 20.1301, which defines dose limits allowable for individual members of the public; 

42 10 CFR 20.1302, which requires compliance with dose limits for individual members of the 

43 public; 10 CFR 20.1701, which requires the use of process or other engineering controls; 

44 10 CFR 20.2002, which requires approval of proposed disposal procedures from relevant state 

45 and federal authorities; 10 CFR 20.2007, which requires compliance with environmental and 

46 health protection regulations; 10 CFR 20, Appendix B, which establishes annual limits on 

47 intakes and DACs; 10 CFR 40.31(h), which defines requirements for applications for uranium or 

48 thorium milling licenses; 10 CFR 40.32(c), which requires that the applicant’s equipment, 

49 facilities, and procedures are adequate to protect health and minimize danger to life and 

50 property; and 10 CFR 40.41(c), which requires that source and byproduct materials shall be 

51 confined to the locations and purposes authorized in the licensed area.”
Description and Design of Proposed Facility

3-50

1 In addition, add: “NRC staff concludes that the applicant’s description of waste management at 

2 the conventional uranium mill or heap leach facility is also in compliance with 10 CFR Part 40, 

3 Appendix A, Criterion 2, which prohibits the proliferation of small waste disposal sites;

4 10 CFR Part 40, Appendix A, Criterion 5E(1), which requires the installation of a leak detection 

5 system for synthetic liners and appropriate testing for clay/soil liners; 10 CFR Part 40, 

6 Appendix A, Criterion 5E(4), which requires hazardous constituents to be neutralized to 

7 promote immobilization; 10 CFR Part 40, Appendix A, Criterion 5G(1), which requires 

8 definition of the chemical and radioactive characteristics of waste solutions; 10 CFR Part 40, 

9 Appendix A, Criterion 7, which requires preoperational monitoring to set baseline parameters; 

10 10 CFR Part 40, Appendix A, Criterion 7A, which requires detection monitoring programs to 

11 set the site-specific groundwater protection standards, respectively; 10 CFR Part 40, 

12 Appendix A, Criterion 8, which provides requirements for control of airborne effluent releases; 

13 10 CFR Part 40, Appendix A, Criterion 10, which requires that long-term surveillance costs need 

14 to be covered by mill operators; 40 CFR Part 146, which provides requirements for deep 

15 injection wells; 40 CFR Part 190, which establishes environmental radiation protection 

16 standards for nuclear power operations; and 40 CFR 440.34, which prohibits discharges of 

17 process wastewater to navigable waters by conventional uranium mill and heap leach extraction 

18 operations.” As a concluding statement, indicate the reason why the applicant’s information is 

19 considered adequate and complete, and why or how that information complies with the 

20 identified regulatory requirements.

21

22 If license conditions are needed, then a more detailed discussion is typically required. Begin 

23 this section with the sentence: “NRC staff has completed its review of the description of waste 

24 management at the conventional uranium mill or heap leach facility in accordance with 

25 Section 3.5.3 of the standard review plan.” Following this sentence, state what information the 

26 applicant provided in the application, including identification of the information that was omitted 

27 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

28 used to list what information the applicant has provided. Next, state why a license condition is 

29 needed, followed by the license condition or conditions. 

30

31 In a separate paragraph following the discussion of the required license condition(s), include the 

32 statement: “Based on the review conducted by NRC staff, the information provided in the 

33 application, supplemented by provisions of the license condition(s) discussed above, meets the 

34 applicable acceptance criteria of Section 3.5.3 of the standard review plan. Therefore, NRC 

35 staff concludes that the applicant’s description of waste management at the conventional 

36 uranium mill or heap leach facility is acceptable and is in compliance with 10 CFR Part 20, 

37 Subpart C, which requires that occupational dose limits need to be controlled; 10 CFR 20.1101, 

38 which requires that an acceptable radiation protection program that achieves ALARA goals is in 

39 place and that a constraint on air emissions, excluding Rn-222 and its decay products, will be 

40 established to limit doses from these emissions; 10 CFR 20.1301, which defines dose limits 

41 allowable for individual members of the public; 10 CFR 20.1302, which requires compliance with 

42 dose limits for individual members of the public; 10 CFR 20.1701, which requires the use of 

43 process or other engineering controls; 10 CFR 20.2002, which requires approval of proposed 

44 disposal procedures from relevant state and federal authorities; 10 CFR 20.2007, which 

45 requires compliance with environmental and health protection regulations; 10 CFR Part 20, 

46 Appendix B, which establishes annual limits on intakes and DACs; 10 CFR 40.31(h), which 

47 defines requirements for applications for uranium or thorium milling licenses; 10 CFR 40.32(c), 

48 which requires that the applicant’s equipments, facilities, and procedures are adequate to 

49 protect health and minimize danger to life and property; 10 CFR 40.41(c), which requires that

50 source and byproduct materials shall be confined to the locations and purposes authorized in 

51 the licensed area.”
Description and Design of Proposed Facility

3-51

1 In addition, add: “NRC staff concludes that the applicant’s description of waste management at 

2 the conventional uranium mill or heap leach facility is also in compliance with 10 CFR Part 40, 

3 Appendix A, Criterion 2, which prohibits the proliferation of small waste disposal sites;

4 10 CFR Part 40, Appendix A, Criterion 5E(1), which requires the installation of a leak detection 

5 system for synthetic liners and appropriate testing for clay/soil liners; 10 CFR Part 40, 

6 Appendix A, Criterion 5E(4), which requires hazardous constituents to be neutralized to promote 

7 immobilization; 10 CFR Part 40, Appendix A, Criterion 5G(1), which requires definition of the 

8 chemical and radioactive characteristics of waste solutions; 10 CFR Part 40, Appendix A, 

9 Criterion 7, which requires preoperational monitoring to set baseline parameters;

10 10 CFR Part 40, Appendix A, Criterion 7A, which requires detection monitoring programs to set 

11 the site-specific groundwater protection standards, respectively; 10 CFR Part 40, Appendix A, 

12 Criterion 8, which provides requirements for control of airborne effluent releases;

13 10 CFR Part 40, Appendix A, Criterion 10, which requires that long-term surveillance costs need 

14 to be covered by mill operators; 40 CFR Part 146, which provides requirements for deep 

15 injection wells; 40 CFR 190, which establishes environmental radiation protection standards for 

16 nuclear power operations; and 40 CFR 440.34, which prohibits discharges of process 

17 wastewater to navigable waters by conventional uranium mill and heap leach extraction 

18 operations.” If not already discussed in the preceding paragraph(s), include a statement or 

19 summation as to why or how the application and license condition(s) jointly comply with the 

20 identified regulatory requirements.

21

22 3.5.5 References

23

24 NRC. Regulatory Guide 1.21, “Measuring, Evaluating, and Reporting Radioactive Material in 

25 Liquid and Gaseous Effluents and Solid Waste.” Rev. 2. Washington, DC: NRC, Office of 

26 Nuclear Regulatory Research. 2009.

27

28 –––––. Regulatory Guide 3.11, “Design, Construction, and Inspection of Embankment 

29 Retention Systems for Uranium Mills.” Rev. 3. Washington, DC: NRC, Office of Nuclear 

30 Regulatory Research. 2008.

31

32 ––––. Regulatory Guide 8.31, “Information Relevant to Ensuring that Occupational Radiation 

33 Exposures at Uranium Mills Will Be as Low as Is Reasonably Achievable.” Rev. 1. 

34 Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002. 

35

36 ––––. Regulatory Guide 3.56, “General Guidance for Designing, Testing, Operating, and 

37 Maintaining Emission Control Devices at Uranium Mills.” Washington, DC: NRC, Office of 

38 Nuclear Regulatory Research. 1986. 

4-1

1 4.0 MANAGEMENT

2

3 4.1 Corporate Organization and Administrative Procedures

4

5 4.1.1 Areas of Review 

6

7 The staff should review the detailed description of the applicant’s proposed organization and 

8 administrative procedures, including a description and/or chart depicting the key positions in 

9 the management structure, and the responsibilities and functions of each procedure with 

10 respect to several key areas. These areas include development, review, approval, and 

11 implementation of, and adherence to, operating procedures, radiation safety programs, 

12 groundwater monitoring programs, quality assurance programs, and routine and nonroutine 

13 maintenance activities. The management structure should also describe how changes to 

14 these key areas are implemented. These key areas include procedures that evaluate 

15 the consequences of a spill or incident/event in relation to the reporting requirements in

16 10 CFR 20.2201, 10 CFR 20.2202, and 10 CFR 40.60. Finally, staff should examine the plans 

17 the applicant proposes for establishing a Safety and Environmental Review Panel (SERP), or 

18 similarly named panel, including the proposed composition and responsibilities of the panel.

19

20 4.1.2 Review Procedures 

21

22 Staff should use the following procedures when reviewing corporate organization and 

23 administrative procedures:

24

25 (1) Verify that the applicant adequately described the corporate organization, clearly defined

26 management responsibilities and authority at each level. This information should meet,

27 in part, the requirements of 10 CFR 20.1101 and 10 CFR 40.32(b).

28

29 (2) If the applicant requests a performance-based license, verify that the applicant has 

30 established a SERP that consists of at least three individuals with specific qualifications 

31 in management, operations, and radiation safety. This information should meet, in part, 

32 the requirements of 10 CFR 20.1101 and 10 CFR 40.32(b).

33

34 (3) Verify that proposed administrative procedures are consistent with Regulatory Guide 8.2, 

35 “Guide for Administrative Practices in Radiation Monitoring,” (U.S. Atomic Energy 

36 Commission, 1973), and with Regulatory Guide 4.15, “Quality Assurance 

37 for Radiological Monitoring Programs (Inception Through Normal Operations to 

38 License Termination)—Effluent Streams and the Environment,” Revision 2 (NRC, 

39 2007). This information should meet, in part, the requirements of 10 CFR 20.1101 

40 and 10 CFR 40.32(c).

41

42 (4) Ensure that sufficient independence exists among operations, maintenance, and 

43 radiological safety staff such that significant safety issues can be raised to 

44 corporate management. This information should meet, in part, the requirements of 

45 10 CFR 20.1101 and 10 CFR 40.32(b).
Management

4-2

1 4.1.3 Acceptance Criteria 

2

3 The corporate organization and administrative procedures are acceptable if they meet the 

4 following criteria: 

5

6 (1) The applicant has adequately described the corporate organization, clearly defining 

7 management responsibilities and authority at each level. Specifically, the radiation 

8 safety officer (RSO), or equivalent, has responsibilities and authority that are consistent 

9 with Regulatory Guide 8.31, “Information Relevant to Ensuring that Occupational 

10 Radiation Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably 

11 Achievable,” Revision 1 (NRC, 2002, Section 1.2). The organizational structure shows 

12 integration among groups that support the operation, maintenance, and safety of the 

13 facility. If the facility is new, ensure that integration between plant construction and plant 

14 management is detailed.

15

16 (2) If the applicant requested a performance-based license, the applicant has established a 

17 SERP that will consist of at least three individuals with specific qualifications in 

18 management, operations, and radiation safety. One member of the SERP will have 

19 expertise in management and will be responsible for implementing managerial and 

20 financial changes. One member will have expertise in operations and/or construction 

21 and will have responsibility for implementing any operational changes. One member will 

22 be the RSO, or equivalent, with the responsibility for assuring that changes conform to

23 radiation safety requirements. Additional members may be included in the SERP, as 

24 appropriate, to address specific technical issues such as health physics, groundwater 

25 hydrology, surface-water hydrology, and specific Earth sciences or other technical 

26 disciplines. Temporary members may include consultants. A description of when 

27 additional members will be used is provided. The applicant states that the SERP will 

28 review all proposed changes and will refer to the NRC those changes that the SERP 

29 determines will require a license amendment.

30

31 (3) The proposed administrative procedures are consistent with Regulatory Guide 8.2 

32 (U.S. Atomic Energy Commission, 1973) and Regulatory Guide 4.15, Revision 2

33 (NRC, 2007). The applicant has provided or has committed to provide written 

34 procedures for dose calculations and measurements, sample collection, sample 

35 management and chain of custody, sample preparation and analysis, data reduction and 

36 recording, data assessment and reporting, and final sample disposal. Procedures are 

37 also provided for addressing support functions, such as operation of process monitors, 

38 training, preparation of quality control samples, corrective actions, audits, and records. 

39 In addition, the applicant has committed to provide training instructions, procedures, or 

40 schedules for the staff performing functions associated with the Quality Assurance

41 program, such as the following:

42

43 (a) Ancillary laboratory functions (including cleaning of glassware, contamination 

44 control, and storage of standards and chemicals);

45

46 (b) Calibration and quality control of instrumentation (including range of activity, 

47 range of energy, and frequency of calibration);

48

49 (c) Internal quality control programs (including frequency, types, acceptance 

50 criteria for the laboratory performance testing samples, and individual 

51 analyst qualifications); and
Management

4-3

1 (d) Timetables for verification and validation of data.

2

3 (4) Sufficient independence exists between operations and maintenance staff and 

4 radiological safety staff such that significant safety issues can be raised to 

5 corporate management. This is demonstrated in an organizational chart and in the 

6 application text. The applicant states what the radiological staff can and cannot do to 

7 maintain radiological safety.

8

9 4.1.4 Evaluation Findings

10

11 If the staff determines that no license conditions are required for the corporate organization and 

12 administrative procedures because the applicant or licensee provided adequate and complete 

13 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

14 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

15 has completed its review of the corporate organization and administrative procedures at the 

16 conventional uranium mill or heap leach facility in accordance with Section 4.1.3 of the standard 

17 review plan.” Following this statement, state what information the applicant provided in the 

18 application. As discussed in the introduction of this SRP, a bullet or sentence format may be 

19 used to list what information the applicant has provided.

20

21 After the description of the information the applicant provided, the following or a similar 

22 statement can be added: “Based on the review conducted by NRC staff, the information 

23 provided in the application meets the applicable acceptance criteria of Section 4.1.3 of the 

24 standard review plan. Therefore, NRC staff concludes that the applicant’s corporate 

25 organization and administrative procedures are acceptable and are in compliance with 

26 10 CFR 20.1101, which requires the use of procedures in the radiation protection program, 

27 and 10 CFR 40.32(b) and (c), which define requirements for the corporate organization and 

28 SERP functions.” As a concluding statement, state the reason why the applicant’s information 

29 is considered adequate and complete, and why or how that information complies with the 

30 identified regulatory requirements.

31

32 If license conditions are needed, then a more detailed discussion is typically required. Begin 

33 this section with the sentence: “NRC staff has completed its review of the corporate 

34 organization and administrative procedures at the conventional uranium mill or heap leach 

35 facility in accordance with Section 4.1.3 of the standard review plan.” Following this statement, 

36 state what information the applicant provided in the application, including identification of the 

37 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

38 bullet or sentence format may be used to list what information the applicant has provided. Next, 

39 state why a license condition is needed, followed by the license condition or conditions. 

40

41 In a separate paragraph following the discussion of the required license condition(s), include the 

42 statement: “Based on the review conducted by NRC staff, the information provided in the 

43 application, supplemented by provisions of the license condition(s) discussed above, meets the 

44 applicable acceptance criteria of Section 4.1.3 of the standard review plan. Therefore, NRC 

45 staff concludes that the applicant’s corporate organization and administrative procedures are

46 acceptable and are in compliance with 10 CFR 20.1101, which requires the use of procedures 

47 in the radiation protection program, and 10 CFR 40.32(b) and (c), which define requirements for 

48 the corporate organization and SERP functions.” If not discussed in the preceding 

49 paragraph(s), include a statement or summation as to why or how the application and license 

50 condition(s) jointly comply with the identified regulatory requirements.

51
4-4

1 4.1.5 References 

2

3 NRC. Regulatory Guide 4.15, “Quality Assurance for Radiological Monitoring Programs 

4 (Inception Through Normal Operations to License Termination)—Effluent Streams and the 

5 Environment.” Rev. 2. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2007.

6

7 –––––. Regulatory Guide 8.31, “Information Relevant to Ensuring That Occupational Radiation 

8 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable.” 

9 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002.

10

11 U.S. Atomic Energy Commission. Regulatory Guide 8.2, “Guide for Administrative Practices in 

12 Radiation Monitoring.” Washington, DC: NRC, Directorate of Regulatory Standards. 1973.

13

14 4.2 Management Control Program 

15

16 4.2.1 Areas of Review

17

18 The staff should review the management control program proposed to ensure that activities 

19 affecting health and safety will be conducted in accordance with written standard operating 

20 procedures, including record keeping and reporting. Staff should evaluate the management 

21 controls and decision bases the SERP will use in deciding when it is necessary to apply for a

22 license amendment. Procedures governing nonroutine work or maintenance that is not covered 

23 by a standard operating procedure, such as use of radiation work permits, should be reviewed.

24

25 The staff should review the applicant’s record keeping and retention plans for:

26

27 • The materials control and tracking program;

28

29 • The radiation protection program;

30

31 • The sampling, survey, and calibration programs;

32

33 • Planned special exposures;

34

35 • The tracking of doses to workers and members of the public;

36

37 • The disposal of source and byproduct materials;

38

39 • The records important to decommissioning the facility, including records of spills or 

40 unusual occurrences involving the spread of contamination, cleanup actions taken, and 

41 the location of remaining contamination; and

42

43 • Inspection records.

44

45 The staff should also review the applicant’s plans and arrangements to identify and maintain the 

46 records that must be retained for the life of the facility and ultimately be transferred to NRC at 

47 the termination of the license.

48

49 While occupational and safety concerns are important and need to be included in the 

50 development of standard operating procedures, NRC regulatory authority is limited to those 
Management

4-5

1 instances where occupational safety concerns may affect radiological operations or accidents. 

2 Detailed procedures for the interface between NRC and the Operational Safety and Health 

3 Administration (OSHA) are included in the “Memorandum of Understanding Between NRC and 

4 the Occupational Safety and Health Administration” (OSHA, 1988).

5

6 4.2.2 Review Procedures 

7

8 The following procedures should be used to review the management control program:

9

10 (1) Verify that all proposed activities that may affect health and safety, including compliance 

11 with any license commitments or conditions, will be conducted in accordance with written 

12 operating procedures.

13

14 Verify that a process will be used to identify and prepare operating procedures for 

15 routine work and that it includes procedures covering all aspects of radiation safety, 

16 routine maintenance activities (especially in radiation areas), and SERP reviews and 

17 activities. This information should meet, in part, the requirements of 10 CFR 20.1101, 

18 10 CFR 40.44, 10 CFR 40.60, 10 CFR 20.2201, and 10 CFR 20.2202.

19

20 (2) Verify that the applicant presents methods for review and approval of nonroutine work or 

21 maintenance activities as required by 10 CFR 20.1101.

22

23 (3) Ensure that procedures governing SERP functions for approvals of all proposed changes 

24 in the facility, the operating procedures, or the conduct of tests or experiments are 

25 appropriately documented and reported. This information should meet, in part, the 

26 requirements of 10 CFR 20.1101.

27

28 (4) Verify that the applicant agrees to maintain and retain records of the receipt, transfer, 

29 and disposal of any source or byproduct material processed or produced at the 

30 licensed facility, for the period set out in the license conditions, or until the Commission 

31 terminates the license. This information should meet, in part, the requirements of 

32 10 CFR 20.2103(b)(4) and 10 CFR 40.60.

33

34 (5) Ensure that the following will be permanently maintained and retained until 

35 license termination:

36

37 (a) Records of onsite radioactive waste disposal;

38

39 (b) Records of certain types of radiation surveys;

40

41 (c) Records included in Regulatory Guide 3.11, “Design, Construction, and 

42 Inspection of Embankment Retention Systems at Uranium Recovery Facilities,”

43 Revision 3 (NRC, 2008); and 

44

45 (d) Records containing information important to decommissioning and reclamation.

46

47 This information should meet, in part, the requirements of 10 CFR 20.2002;

48 10 CFR 20.2007; 10 CFR 20.2103(b)(4); 10 CFR 40.36(f)(4); and 10 CFR Part 40, 

49 Appendix A, Criteria 8 and 8A.

50
4-6

1 (6) Verify that the applicant demonstrates that records, including records received from a 

2 previous owner or applicant, will be provided to a new owner or new applicant if the 

3 property or license is transferred, or to NRC after license termination. Ensure that all 

4 records will be maintained as hard copy originals or as copies on microfiche, or will be 

5 electronically protected, and will be readily retrievable for NRC inspection. This 

6 information should meet, in part, the requirements of 10 CFR 20.2103(b)(4) and 

7 10 CFR 40.61(d) and (e).

8

9 (7) Verify that reports of spills, surface impoundment leaks, or process chemical leaks will 

10 be made to the NRC project manager (or Operations Center, if required) by telephone or 

11 electronic mail (e-mail) within 48 hours of the event. This information should meet, in 

12 part, the requirements of 10 CFR 20.2202.

13

14 (8) Verify that theft or loss of material in an aggregate quantity greater than 1,000 times the 

15 quantity specified in Appendix C to Part 20 is reported to the NRC project manager (or 

16 Operations Center, if required) by telephone or by electronic mail within 48 hours of the 

17 event. Verify that within 30 days after the occurrence of any lost, stolen, or missing 

18 licensed material becomes known to the licensee in quantities greater than 10 times the 

19 quantity specified in 10 CFR Part 20, Appendix C is reported in writing and includes the 

20 quantity that is still missing at this time. Verify that the discovery of any incident in which 

21 an attempt has been made, or is believed to have been made, to create a theft or 

22 unlawful diversion of more than 6.8 kg [15 lb] at any one time or more than 68 kg [150 lb] 

23 of such material in any one calendar year is reported to the NRC project manager (or 

24 Operations Center, if required). This information should meet, in part, the requirements 

25 of 10 CFR 20.2201 and 10 CFR 40.64(c).

26

27 (9) Ensure that the applicant has committed to submit an annual report to NRC that 

28 includes the as low as is reasonably achievable (ALARA) audit report, monitoring 

29 data, corrective action program report, semiannual effluent and monitoring reports, and 

30 the SERP determinations. This information should meet, in part, the requirements of 

31 10 CFR 20.2103(b)(4); 10 CFR 40.61(d) and (e); and 10 CFR 40.65.

32

33 4.2.3 Acceptance Criteria 

34

35 The management control program is acceptable if it meets the following criteria:

36

37 (1) The proposed management control program is sufficient to ensure that any activities 

38 affecting health and safety, including compliance with any license commitments or 

39 conditions, will be conducted in accordance with written standard operating procedures. 

40 The applicant describes the process for identifying and developing standard operating 

41 procedures for routine work, and the review and approval process the radiation safety 

42 staff will use to modify standard operating procedures when appropriate.

43

44 Subsequent NRC inspections will ensure that standard operating procedures are 

45 adequate and applied correctly. Standard operating procedures for radiation safety are 

46 consistent with Regulatory Guide 8.31, “Information Relevant to Ensuring that 

47 Occupational Radiation Exposures at Uranium Recovery Facilities Will Be as Low as Is 

48 Reasonably Achievable,” Revision 1 (NRC, 2002, Section 2).

49

50 (2) The applicant presents methods for review and approval of nonroutine work or 

51 maintenance activities by the radiation safety staff. The methods include the preparation 
Management

4-7

1 and issuance of radiation work permits for activities where standard operating 

2 procedures do not apply. For example, repair of a malfunctioning vacuum dryer is 

3 considered to be nonroutine work and will be performed after the radiation work permit 

4 has been approved by radiation safety, industrial safety, quality assurance, and 

5 line management.

6

7 (3) A detailed review of SERP composition is addressed in Section 4.1 of this SRP. 

8 Procedures governing the functioning of the SERP ensure that approvals of any 

9 changes in the facility, the operating procedures, or the conduct of tests or experiments 

10 are appropriately documented and reported. The applicant will verify that these 

11 changes, tests, or experiments may be implemented without obtaining a license 

12 amendment pursuant to 10 CFR 40.44, so long as the change, test, or experiment 

13 does not:

14

15 (a) Create a possibility for an accident of a different type than previously evaluated in 

16 the license application (as updated);

17

18 (b) Create a possibility for a malfunction of a structure, system, or component with a 

19 different result than previously evaluated in the license application (as 

20 updated); or

21

22 (c) Result in a departure from the method of evaluation described in the license 

23 application (as updated) used in establishing the final safety evaluation report or 

24 technical evaluation reports or other analyses and evaluations for 

25 license amendments.

26

27 (d) Amend a license condition.

28

29 SERP records will include evaluations of all proposed changes to operations and the 

30 SERP decision of whether the change requires a license amendment. SERP records 

31 will also include written health and safety evaluations the SERP makes that provide the 

32 basis for determining whether changes, tests, or experiments were implemented in 

33 accordance with the basis described in Section 4.1.3 in this SRP. The applicant states 

34 that all SERP reports shall be sufficiently comprehensive to allow staff to thoroughly 

35 evaluate the change, test, or experiment.

36

37 (4) The record keeping and retention plans demonstrate that the applicant will maintain and 

38 retain records of the receipt, transfer, and disposal of any source or byproduct material 

39 processed or produced at the licensed facility for the period set out in the license, or until 

40 the Commission terminates the license. The proposed record keeping and retention 

41 programs are adequate to ensure that the applicant will be able to track, control, and 

42 demonstrate control of the source and byproduct material at the site, such that onsite 

43 and offsite dose limits will not be exceeded.

44

45 (5) The following will be permanently maintained and retained until license termination: 

46

47 (a) Records of onsite radioactive waste disposal, such as by deep well injection, land 

48 application, or burial.

49

50
4-8

1 (b) Records of radiation measurements and surveys required by 

2 10 CFR 20.2103(b)(4), including:

3

4 (i) Surveys to measure radiation dose;

5

6 (ii) Measurements and calculations used to determine individual intakes of 

7 radioactive materials;

8

9 (iii) Measurements resulting from air sampling, surveys, and bioassays; and

10

11 (iv) Measurements and calculations used to evaluate the release of 

12 radioactive effluents.

13

14 (c) Records required by 10 CFR Part 40, Appendix A, Criteria 8 and 8A as discussed

15 in Regulatory Guide 3.11, Revision 3 (NRC, 2008).

16

17 (d) Records containing information important to decommissioning and 

18 reclamation, including:

19

20 (i) Descriptions of any spills, leaks, contamination events, or unusual 

21 occurrences, including the dates, locations, areas, or facilities affected; 

22 assessments of hazards; corrective and cleanup actions taken; 

23 assessment of cleanup effectiveness and the location of any remaining 

24 contamination; nuclides involved; quantities, forms and concentrations, 

25 and descriptions of hazardous constituents; descriptions of inaccessible 

26 areas that cannot be cleaned up; and sketches, diagrams, or drawings 

27 marked to show areas of contamination and places where measurements 

28 were made (significant spills that will be included are any radiological 

29 spills that have the potential to exceed site cleanup standards and any 

30 radiological spill that leaves the site; a license condition will be 

31 established to this effect).

32

33 (ii) Information related to site characterization; residual soil contamination 

34 levels; onsite locations used for burials of radioactive materials; hydrology 

35 and geology, with particular emphasis on conditions that could contribute 

36 to groundwater or surface-water contamination; preoperational 

37 background radiation levels at and near the site; and locations of waste

38 water ponds and lagoons.

39

40 (iii) As-built drawings or photographs of structures, equipment, restricted 

41 areas, areas where radioactive materials are stored, and any 

42 modifications showing the locations of these structures and systems 

43 through time.

44

45 (iv) Drawings of inaccessible, potentially contaminated areas, including 

46 features such as buried pipes or pipelines.

47

48 The applicant will maintain these records, such as descriptions of spills and other 

49 unusual occurrences and retain them in an identifiable or, preferably, separate file with 

50 adequate safeguards against tampering and loss.

51
Management

4-9

1 (6) The applicant demonstrates a plan to maintain the records and provides the records 

2 (i) to a new owner or new applicant if the property or license is transferred or (ii) to NRC 

3 after license termination. These records include any such records received from a 

4 previous owner or applicant. The records will be maintained as hard copy originals or as 

5 copies on microfiche, or will be electronically protected, and will be readily retrievable for 

6 NRC inspection.

7

8 (7) The applicant commits to making reports of spills; surface impoundment leaks; and leaks 

9 of source, byproduct material, or process chemicals to the NRC project manager 

10 (or Operations Center if required) by telephone or electronic mail (e-mail) within 48 hours 

11 of the event. This notification will be followed within 30 days by submittal of a written 

12 report to NRC detailing the conditions leading to the spill or incident/event, corrective 

13 actions taken, and results achieved.

14

15 (8) The applicant commits to reporting the theft or loss of source material in an aggregate 

16 quantity greater than 1,000 times the quantity specified in Appendix C to Part 20 to the 

17 NRC project manager (or Operations Center, if required) by telephone or by electronic 

18 mail within 48 hours of the event. The applicant further commits to reporting in writing, 

19 within 30 days after the occurrence, any lost, stolen, or missing licensed material that 

20 becomes known to the licensee in quantities greater than 10 times the quantity specified 

21 in 10 CFR 20, Appendix C and includes the quantity that is still missing at this time. The 

22 applicant also commits to reporting the discovery of any incident in which an attempt has 

23 been made or is believed to have been made to create a theft or unlawful diversion of 

24 more than 6.8 kg [15 lb] at any one time or more than 68 kg [150 lb] of such material in 

25 any one calendar year to the NRC project manager (or Operations Center, if required). 

26

27 (9) An annual report will be submitted to NRC that includes the ALARA audit report, 

28 monitoring data, the corrective action program report, the semiannual effluent and 

29 monitoring reports, and the SERP determinations.

30

31 4.2.4 Evaluation Findings 

32

33 If the staff determines that no license conditions are required for the management control 

34 program because the applicant or licensee provided adequate and complete information that 

35 fully addresses all relevant regulatory requirements, typically a single paragraph is sufficient for 

36 the evaluation findings section. Begin the section with the sentence: “NRC staff has completed 

37 its review of the management control program at the conventional uranium mill or heap leach 

38 facility in accordance with Section 4.2.3 of the standard review plan.” Following this statement, 

39 state what information the applicant provided in the application. As discussed in the introduction 

40 of this SRP, a bullet or sentence format may be used to list what information the applicant 

41 has provided. 

42

43 After the description of the information the applicant provided, the following or a similar 

44 statement can be added: “Based on the review conducted by NRC staff, the information 

45 provided in the application meets the applicable acceptance criteria of Section 4.2.3 of the 

46 standard review plan. Therefore, NRC staff concludes that the applicant’s management control 

47 program is acceptable and is in compliance with 10 CFR 20.1101, which defines radiation 

48 protection program requirements; 10 CFR 20.2002, which describes requirements of obtaining 

49 approval of proposed disposal procedures; 10 CFR 20.2007, which requires compliance with 

50 environmental and health protection regulations; 10 CFR 20.2103(b)(4), which describes record 

51 retention requirements; 10 CFR 20.2201, which defines requirements for record keeping; 
4-10

1 10 CFR 20.2202, which defines requirements for reporting incidents; 10 CFR 40.36(f)(4), 

2 which describes requirements for records of the cost estimate performed for the 

3 decommissioning funding plan and records of the funding method; 10 CFR 40.61(d) and 

4 (e), which also define requirements for record keeping; 10 CFR 40.44, which describes 

5 requirements for amending the license; 10 CFR 40.60, which describes reporting requirements; 

6 10 CFR 40.64(c), which describes reporting requirements for stolen or unlawful diversion of 

7 source material; 10 CFR 40.65, which defines requirements for effluent record keeping; and 

8 10 CFR Part 40, Appendix A, Criteria 8 and 8A, which specify documentation requirements for 

9 airborne effluents and waste retention systems.” As a concluding statement, state the reason 

10 why the applicant’s information is considered adequate and complete, and why or how that 

11 information complies with the identified regulatory requirements.

12

13 If license conditions are needed, then a more detailed discussion is typically required. Begin 

14 this section with the sentence: “NRC staff has completed its review of the management control 

15 program at the conventional uranium mill or heap leach facility in accordance with Section 4.2.3 

16 of the standard review plan.” Following this statement, state what information the applicant 

17 provided in the application, including identification of the information that was omitted or 

18 inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

19 used to list what information the applicant has provided. Next, state why a license condition is 

20 needed, followed by the license condition or conditions. 

21

22 In a separate paragraph following the discussion of the required license condition(s) include the 

23 statement: “Based on the review conducted by NRC staff, the information provided in the 

24 application, supplemented by provisions of the license condition(s) discussed above, meets the 

25 applicable acceptance criteria of Section 4.2.3 of the standard review plan. Therefore, NRC 

26 staff concludes that the applicant’s management control program is acceptable and is in 

27 compliance with 10 CFR 20.1101, which defines radiation protection program requirements; 

28 10 CFR 20.2002, which describes requirements of obtaining approval of proposed disposal 

29 procedures; 10 CFR 20.2007, which requires compliance with environmental and health 

30 protection regulations; 10 CFR 20.2103(b)(4), which describes record retention requirements; 

31 10 CFR 20.2201, which defines requirements for record keeping; 10 CFR 20.2202, which 

32 defines requirements for reporting incidents; 10 CFR 40.36(f)(4), which describes requirements 

33 for records of the cost estimate performed for the decommissioning funding plan and records of 

34 the funding method; 10 CFR 40.61(d) and (e), which also define requirements for record 

35 keeping; 10 CFR 40.44, which describes requirements for amending the license; 10 CFR 40.60, 

36 which describes reporting requirements; 10 CFR 40.64(c), which describes reporting 

37 requirements for stolen or unlawful diversion of source material; 10 CFR 40.65, which defines 

38 requirements for effluent record keeping; and 10 CFR Part 40, Appendix A, Criteria 8 and 8A, 

39 which specify documentation requirements for airborne effluents and waste retention 

40 systems.” If not discussed in the preceding paragraph(s), include a statement or summation 

41 as to why or how the application and license condition(s) jointly comply with the identified 

42 regulatory requirements.

43

44 4.2.5 References

45

46 NRC. Regulatory Guide 3.11, “Design, Construction, and Inspection of Embankment Retention 

47 Systems at Uranium Recovery Facilities.” Rev. 3. Washington, DC: NRC, Office of Nuclear 

48 Regulatory Research. 2008. 

49
Management

4-11

1 –––––. Regulatory Guide 8.31, “Information Relevant to Ensuring That Occupational Radiation 

2 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable.” 

3 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002. 

4

5 OSHA. “Memorandum of Understanding Between the U.S. Nuclear Regulatory Commission 

6 and the Occupational Safety and Health Administration.” 1988. <http://www.osha.gov/pls/

7 oshaweb/owadisp.show_document?p_table=MOU&p_id=233> (12 April 2011).

8

9 4.3 Management Audit and Inspection Program 

10

11 4.3.1 Areas of Review 

12

13 The staff should review the proposed management audit, inspection, and ALARA programs, 

14 including the frequencies, types, and scopes of reviews and inspections; action levels; 

15 corrective action measures; and the responsibilities of each participant. The staff should also 

16 review the program for ensuring that employee exposures (to both airborne and external 

17 radiation) and effluent releases are ALARA.

18

19 4.3.2 Review Procedure 

20

21 Staff should verify that the proposed frequencies, types, and scopes of reviews and inspections; 

22 action levels; and corrective action measures of the management audit and inspection program 

23 are acceptable to implement the proposed controls and that management responsibilities for 

24 audit and inspection are adequately defined. This information should meet, in part, the 

25 requirements of 10 CFR 20.1701; 10 CFR 20.1702; 10 CFR 20.1101; 10 CFR 40.32(b), (c), 

26 and (d); and 10 CFR Part 40, Appendix A, Criteria 8 and 8A.

27

28 4.3.3 Acceptance Criterion

29

30 The management audit and inspection program, including the proposed frequencies, types, and 

31 scopes of reviews and inspections; action levels; and corrective action measures, is 

32 acceptable if: 

33

34 (a) The management responsibilities for audit and inspection are adequately defined. 

35

36 (b) The yellowcake drying and packaging operations are in accordance with

37 10 CFR Part 40, Appendix A, Criterion 8, and inspection of waste retention systems

38 is in accordance with 10 CFR Part 40, Appendix A, Criterion 8A. 

39

40 (c) The embankment systems inspection program is consistent with Regulatory Guide 3.11, 

41 “Design, Construction, and Inspection of Embankment Retention Systems at Uranium 

42 Recovery Facilities,” Revision 3 (NRC, 2008). 

43

44 (d) The annual ALARA audit program is consistent with Regulatory Guide 8.31, “Information 

45 Relevant to Ensuring That Occupational Radiation Exposures at Uranium Recovery 

46 Facilities Will Be as Low as Is Reasonably Achievable,” Revision 1, (NRC, 2002).

47
4-12

1 4.3.4 Evaluation Findings

2

3 If the staff determines that no license conditions are required for the management audit and 

4 inspection program because the applicant or licensee provided adequate and complete 

5 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

6 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

7 has completed its review of the management audit and inspection program at the conventional 

8 uranium mill or heap leach facility in accordance with Section 4.3.3 of the standard review plan.” 

9 Following this statement, state what information the applicant provided in the application. As 

10 discussed in the introduction of this SRP, a bullet or sentence format may be used to list what

11 information the applicant has provided. 

12

13 After the description of the information the applicant provided, the following or a similar 

14 statement can be added: “Based on the review conducted by NRC staff, the information 

15 provided in the application meets the applicable acceptance criteria of Section 4.3.3 of the 

16 standard review plan. Therefore, NRC staff concludes that the applicant’s management audit 

17 and inspection program is acceptable and is in compliance with 10 CFR 20.1101, which 

18 requires maintaining radiation exposure limits ALARA; 10 CFR 20.1701 and 10 CFR 20.1702, 

19 which require the use of process or other engineering measures to control the concentrations of 

20 radioactive material in the air; 10 CFR 40.32(b), (c), and (d), which require management audits 

21 to ensure protection of health and minimize danger to life and property; and 10 CFR Part 40, 

22 Appendix A, Criteria 8 and 8A, which require inspection of yellowcake drying and packaging 

23 operations and waste retention systems.” As a concluding statement, state the reason why the 

24 applicant’s information is considered adequate and complete, and why or how that information 

25 complies with the identified regulatory requirements.

26

27 If license conditions are needed, then a more detailed discussion is typically required. Begin 

28 this section with the sentence: “NRC staff has completed its review of the management audit 

29 and inspection program at the conventional uranium mill or heap leach facility in accordance 

30 with Section 4.3.3 of the standard review plan.” Following this statement, state what information 

31 the applicant provided in the application, including identification of the information that was 

32 omitted or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format 

33 may be used to list what information the applicant has provided. Next, state why a license 

34 condition is needed, followed by the license condition or conditions.

35

36 In a separate paragraph following the discussion of the required license condition(s), include the 

37 statement: “Based on the review conducted by NRC staff, the information provided in the 

38 application, supplemented by provisions of the license condition(s) discussed above, meets the 

39 applicable acceptance criteria of Section 4.3.3 of the standard review plan. Therefore, NRC 

40 staff concludes that the applicant’s management audit and inspection program is acceptable 

41 and is in compliance with 10 CFR 20.1101, which requires maintaining radiation exposure 

42 limits ALARA; 10 CFR 20.1701 and 10 CFR 20.1702, which require the use of process or 

43 other engineering measures to control the concentrations of radioactive material in the air; 

44 10 CFR 40.32(b), (c), and (d), which require management audits to ensure protection of 

45 health and minimize danger to life and property; and 10 CFR Part 40, Appendix A, Criteria 8 

46 and 8A, which require inspection of yellowcake drying and packaging operations and waste 

47 retention systems.” If not discussed in the preceding paragraph(s), include a statement or 

48 summation as to why or how the application and license condition(s) jointly comply with the 

49 identified regulatory requirements.

50

51
Management

4-13

1 4.3.5 References

2

3 NRC. Regulatory Guide 3.11, “Design, Construction, and Inspection of Embankment Retention 

4 Systems at Uranium Recovery Facilities.” Rev. 3. Washington, DC: NRC, Office of Nuclear 

5 Regulatory Research. 2008. 

6

7 –––––. Regulatory Guide 8.31, “Information Relevant to Ensuring That Occupational Radiation 

8 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable.” 

9 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002. 

10

11 4.4 Qualifications for Personnel Conducting the Radiation 

12 Safety Program

13

14 4.4.1 Areas of Review 

15

16 The staff should review descriptions of the minimum qualifications and experience levels 

17 required for personnel who will be assigned the responsibility for developing, conducting, and 

18 administering the radiation safety program. The staff should also review the qualifications of 

19 people specifically proposed for these positions.

20

21 4.4.2 Review Procedure

22

23 When reviewing the qualifications for personnel conducting the radiation safety program, staff 

24 should ensure that the personnel meet minimum qualifications and experience for radiation 

25 safety staff that are consistent with Regulatory Guide 8.31, “Information Relevant to Ensuring 

26 that Occupational Radiation Exposures at Uranium Recovery Facilities Will Be as Low as Is 

27 Reasonably Achievable,” Revision 1 (NRC, 2002, Section 2.4). This information should meet, in 

28 part, the requirements of 10 CFR 20.1101 and 10 CFR 40.32(b).

29

30 4.4.3 Acceptance Criterion

31

32 The qualifications of radiation safety personnel are acceptable if the personnel meet minimum 

33 qualifications and experience for radiation safety staff consistent with Regulatory Guide 8.31, 

34 Revision 1 (NRC, 2002, Section 2.4), and the qualifications of the people specifically proposed 

35 for these positions are consistent with the minimum qualifications and experience levels. If the 

36 licensee proposes to use a designee in the absence of the RSO who does not meet the 

37 education and experience of the RSO or health physics technician as recommended in 

38 Regulatory Guide 8.31, the minimum qualifications of the designee should be described in the 

39 license application.

40

41 4.4.4 Evaluation Findings 

42

43 If the staff determines that no license conditions are required for the qualifications of the facility 

44 personnel conducting the radiation safety program because the applicant or licensee provided 

45 adequate and complete information that fully addresses all relevant regulatory requirements, 

46 typically a single paragraph is sufficient for the evaluation findings section. Begin the section 

47 with the sentence: “NRC staff has completed its review of the qualifications of facility personnel 

48 conducting the radiation safety program at the conventional uranium mill or heap leach facility in 

49 accordance with Section 4.4.3 of the standard review plan.” Following this statement, state 

50 what information the applicant provided in the application. As discussed in the introduction 
4-14

1 of this SRP, a bullet or sentence format may be used to list what information the applicant

2 has provided. 

3

4 After the description of the information the applicant provided, the following or a similar 

5 statement can be added: “Based on the review conducted by NRC staff, the information 

6 provided in the application meets the applicable acceptance criteria of Section 4.4.3 of the 

7 standard review plan. Therefore, NRC staff concludes that the applicant’s qualifications of 

8 facility personnel conducting the radiation safety program is acceptable and is in compliance 

9 with 10 CFR 20.1101, which defines radiation protection program requirements, and 

10 10 CFR 40.32(b), which provides requirements for applicant qualifications.” As a 

11 concluding statement, state the reason why the applicant’s information is considered 

12 adequate and complete, and why or how that information complies with the identified 

13 regulatory requirements.

14

15 If license conditions are needed, then a more detailed discussion is typically required. Begin 

16 this section with the sentence: “NRC staff has completed its review of the qualifications of 

17 facility personnel conducting the radiation safety program at the conventional uranium mill or 

18 heap leach facility in accordance with Section 4.4.3 of the standard review plan.” Following 

19 this statement, state what information the applicant provided in the application, including 

20 identification of the information that was omitted or inadequate. As discussed in the introduction

21 of this SRP, a bullet or sentence format may be used to list what information the applicant 

22 has provided. Next, state why a license condition is needed, followed by the license condition 

23 or conditions. 

24

25 In a separate paragraph following the discussion of the required license condition(s), include the 

26 statement: “Based on the review conducted by NRC staff, the information provided in the 

27 application, supplemented by provisions of the license condition(s) discussed above, meets the 

28 applicable acceptance criteria of Section 4.4.3 of the standard review plan. Therefore, NRC 

29 staff concludes that the applicant’s qualifications of facility personnel conducting the radiation 

30 safety program is acceptable and is in compliance with 10 CFR 20.1101, which defines radiation 

31 protection program requirements, and 10 CFR 40.32(b), which provides requirements for 

32 applicant qualifications.” If not discussed in the preceding paragraph(s), include a statement or 

33 summation as to why or how the application and license condition(s) jointly comply with the 

34 identified regulatory requirements.

35

36 4.4.5 Reference

37

38 NRC. Regulatory Guide 8.31, “Information Relevant to Ensuring that Occupational Radiation 

39 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable.” 

40 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002.

41

42 4.5 Radiation Safety Training

43

44 4.5.1 Areas of Review 

45

46 The staff should review the proposed radiation safety training program, including the content of 

47 the initial training or indoctrination, testing, on-the-job training, and the extent and frequency of 

48 retraining. The staff should also review the proposed written radiological safety instructions that 

49 will be provided to employees to include personal hygiene, contamination surveying before 
Management

4-15

1 eating or leaving the operating area, requirements for personal monitoring devices and 

2 respirators, housekeeping requirements, spill cleanup procedures, and emergency actions.

3

4 4.5.2 Review Procedure 

5

6 When reviewing radiation safety training, staff should verify that the applicant presents the 

7 training program. Such presentation should discuss the personnel to be trained, classroom and 

8 on-the-job training, and personnel evaluations to determine proficiency. Staff should also 

9 review procedures to prevent erosion of the radiation safety program.

10

11 This information should meet, in part, the requirements of 10 CFR 20.1101 

12 and 10 CFR 40.32(b).

13

14 4.5.3 Acceptance Criterion

15

16 The applicant’s radiation safety training program is adequate and is acceptable to provide 

17 radiological safety instructions to the employees if the radiation safety training program is 

18 consistent with the following guidance documents:

19

20 (a) Regulatory Guide 8.31, “Information Relevant to Ensuring that Occupational Radiation 

21 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable,”

22 Revision 1 (NRC, 2002, Section 2.5). This guide recommends that before beginning 

23 their jobs, all new employees will be instructed, through an established course, in the 

24 inherent risks of exposure to radiation and the fundamentals of protection against 

25 exposure to uranium and its daughters.

26

27 (b) Regulatory Guide 8.13, “Instruction Concerning Prenatal Radiation Exposure,”

28 Revision 3 (NRC, 1999). This guide provides a basis for protection of the fetus.

29

30 (c) Regulatory Guide 8.29, “Instruction Concerning Risks from Occupational Radiation 

31 Exposure,” Revision 1 (NRC, 1996). This guide provides a basis for training employees 

32 on the risks from radiation exposure in the work place.

33

34 The applicant may propose alternative training guidelines provided that the applicant 

35 demonstrates that these alternative guidelines will not increase the risk of an accident or 

36 exposures to workers or members of the general public. If the licensee proposes to use a 

37 designee in the absence of the RSO who does not meet the education and experience of the 

38 RSO or health physics technician as recommended in Regulatory Guide 8.31, the minimum 

39 qualifications of the designee should be described in the license application. 

40

41 4.5.4 Evaluation Findings 

42

43 If the staff determines that no license conditions are required for the radiation safety training 

44 program because the applicant or licensee provided adequate and complete information that 

45 fully addresses all relevant regulatory requirements, typically a single paragraph is sufficient for 

46 the evaluation findings section. Begin the section with the sentence: “NRC staff has completed 

47 its review of the radiation safety training program at the conventional uranium mill or heap leach 

48 facility in accordance with Section 4.5.3 of the standard review plan.” Following this statement, 

49 state what information the applicant provided in the application. As discussed in the introduction 
4-16

1 of this SRP, a bullet or sentence format may be used to list what information the applicant 

2 has provided. 

3

4 After the description of the information the applicant provided, the following or similar statement 

5 can be added: “Based on the review conducted by NRC staff, the information provided in the 

6 application meets the applicable acceptance criteria of Section 4.5.3 of the standard review 

7 plan. Therefore, NRC staff concludes that the applicant’s radiation safety training program is 

8 acceptable and is in compliance with 10 CFR 20.1101, which defines radiation protection 

9 program requirements, and 10 CFR 40.32(b), as it relates to applicant qualifications through 

10 training.” As a concluding statement, state the reason why the applicant’s information is 

11 considered adequate and complete, and why or how that information complies with the 

12 identified regulatory requirements.

13

14 If license conditions are needed, then a more detailed discussion is typically required. Begin 

15 this section with the sentence: “NRC staff has completed its review of the radiation safety 

16 training program at the conventional uranium mill or heap leach facility in accordance with 

17 Section 4.5.3 of the standard review plan.” Following this statement, state what information the 

18 applicant provided in the application, including identification of the information that was omitted 

19 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

20 used to list what information the applicant has provided. Next, state why a license condition is 

21 needed, followed by the license condition or conditions.

22

23 In a separate paragraph following the discussion of the required license condition(s), include the 

24 statement: “Based on the review conducted by NRC staff, the information provided in the 

25 application, supplemented by provisions of the license condition(s) discussed above, meets the 

26 applicable acceptance criteria of Section 4.5.3 of the standard review plan. Therefore, NRC 

27 staff concludes that the applicant’s radiation safety training program is acceptable and is in 

28 compliance with 10 CFR 20.1101, which defines radiation protection program requirements, and 

29 10 CFR 40.32(b), as it relates to applicant qualifications through training.” If not discussed in

30 the preceding paragraph(s), include a statement or summation as to why or how the application 

31 and license condition(s) jointly comply with the identified regulatory requirements.

32

33 4.5.5 References 

34

35 NRC. Regulatory Guide 8.31, “Information Relevant to Ensuring That Occupational Radiation 

36 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable.” 

37 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002.

38

39 –––––. Regulatory Guide 8.13, “Instruction Concerning Prenatal Radiation Exposure.” Rev. 3. 

40 Washington, DC: NRC, Office of Nuclear Regulatory Research. 1999. 

41

42 –––––. Regulatory Guide 8.29, “Instruction Concerning Risks from Occupational Radiation 

43 Exposure.” Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 1996. 

44

45 4.6 Security

46

47 4.6.1 Areas of Review 

48

49 The staff should review the security measures proposed to prevent unauthorized entry into the 

50 controlled area.
Management

4-17

1 4.6.2 Review Procedure

2

3 When reviewing the applicant’s security program, staff should verify that the security program 

4 has acceptable passive controls, such as fencing and warning signage, and active controls, 

5 such as daily inspections and locks for plant buildings. This information should meet, in part, 

6 the requirements of 10 CFR Part 20, Subparts H and J, 10 CFR 20.1801, and 10 CFR 20.1802.

7

8 4.6.3 Acceptance Criterion

9

10 The security program is acceptable if the applicant has acceptable passive controls, such as 

11 fencing and warning signage, and active controls, such as daily inspections and locks for plant 

12 buildings. The proposed security measures should be sufficient to prevent unauthorized entry 

13 into the controlled and restricted areas.

14

15 4.6.4 Evaluation Findings

16

17 If the staff determines that no license conditions are required for the security measures because 

18 the applicant or licensee provided adequate and complete information that fully addresses all 

19 relevant regulatory requirements, typically a single paragraph is sufficient for the evaluation 

20 findings section. Begin the section with the sentence: “NRC staff has completed its review of 

21 the security measures at the conventional uranium mill or heap leach facility in accordance with

22 Section 4.6.3 of the standard review plan.” Following this statement, state what information the 

23 applicant provided in the application. As discussed in the introduction of this SRP, a bullet or 

24 sentence format may be used to list what information the applicant has provided. 

25

26 After the description of the information the applicant provided, the following or a similar 

27 statement can be added: “Based on the review conducted by NRC staff, the information 

28 provided in the application meets the applicable acceptance criteria of Section 4.6.3 of the 

29 standard review plan. Therefore, NRC staff concludes that the applicant’s security measures 

30 are acceptable and are in compliance with 10 CFR Part 20, Subpart H, which provides 

31 requirements for control of access to buildings containing airborne radioactive material;

32 10 CFR 20.1801, which provides requirements for the security of stored material,

33 10 CFR 20.1802, which provides requirements for the control of material not in storage; 

34 and 10 CFR Part 20, Subpart J, which provides requirements for posting warning signage 

35 for potential exposure to radiation.” As a concluding statement, state the reason why the 

36 applicant’s information is considered adequate and complete, and why or how that information 

37 complies with the identified regulatory requirements.

38

39 If license conditions are needed, then a more detailed discussion is typically required. Begin 

40 this section with the sentence: “NRC staff has completed its review of the security measures at 

41 the conventional uranium mill or heap leach facility in accordance with Section 4.6.3 of the 

42 standard review plan.” Following this statement, state what information the applicant provided 

43 in the application, including identification of the information that was omitted or inadequate. As 

44 discussed in the introduction of this SRP, a bullet or sentence format may be used to list what

45 information the applicant has provided. Next, state why a license condition is needed, followed 

46 by the license condition or conditions. 

47

48 In a separate paragraph following the discussion of the required license condition(s), include the 

49 statement: “Based on the review conducted by NRC staff, the information provided in the 

50 application, supplemented by provisions of the license condition(s) discussed above, meets the 
4-18

1 applicable acceptance criteria of Section 4.6.3 of the standard review plan. Therefore, NRC 

2 staff concludes that the applicant’s security measures are acceptable and are in compliance 

3 with 10 CFR Part 20, Subpart H, which provides requirements for control of access to buildings 

4 containing airborne radioactive material; 10 CFR 20.1801, which provides requirements for the 

5 security of stored material, 10 CFR 20.1802, which provides requirements for the control of 

6 material not in storage; and 10 CFR Part 20, Subpart J, which provides requirements for posting 

7 warning signage for potential exposure to radiation.” If not discussed in the preceding 

8 paragraph(s), include a statement or summation as to why or how the application and license 

9 condition(s) jointly comply with the identified regulatory requirements.

10

11 4.6.5 References

12

13 None.

14

15 4.7 Quality Assurance 

16

17 4.7.1 Areas of Review 

18

19 The staff should review the quality assurance programs proposed for all radiological, 

20 nonradiological, and effluent monitoring programs. Nonradiological quality assurance 

21 programs should be consistent with guidance in U.S. Environmental Protection Agency (EPA)

22 QA/R–5 (2001).

23

24 4.7.2 Review Procedures 

25

26 Staff should use the following procedures when reviewing quality assurance:

27

28 (1) Ensure that the radiological and nonradiological quality assurance program has 

29 been established and applied to all radiological, nonradiological, and effluent 

30 monitoring programs.

31

32 (2) Verify that all reporting and record keeping will be done in conformance with the criteria 

33 presented in Section 4.2.2 of this SRP.

34

35 (3) For license renewal applications, ensure that historical quality assurance 

36 program results are included through the most recent reporting period preceding 

37 application submittal.

38

39 This information should meet, in part, the requirements of 10 CFR 20.1101.

40

41 4.7.3 Acceptance Criteria 

42

43 The quality assurance program is acceptable if it meets the following criteria: 

44

45 (1) The radiological quality assurance program has been established and applied to all 

46 radiological and effluent monitoring programs during the preoperational, operational, and 

47 decommissioning periods. The proposed radiological quality assurance plan is 

48 consistent with guidance provided in Regulatory Guide 4.14, “Radiological Effluent and 

49 Environmental Monitoring at Uranium Mills,” Revision 1 (NRC, 1980, Sections 3 and 6) 

50 and Regulatory Guide 4.15, “Quality Assurance for Radiological Monitoring Programs 
Management

4-19

1

2

3 (Inception Through Normal Operations to License Termination)—Effluent Streams and 

4 the Environment,” Revision 2 (NRC, 2007). The proposed radiological quality assurance 

5 program is sufficient to limit radiation exposures and radioactive releases to ALARA and 

6 is in conformance with regulatory requirements identified in 10 CFR Part 20.

7

8 The quality assurance program contains or encompasses the following elements:

9

10 (a) Formal delineation of organizational structure, management responsibilities, and 

11 the organizational relationship between these individuals and the person who has 

12 ultimate authority for the quality assurance program as discussed in Section 4.1

13 of this SRP.

14

15 (b) Both review and approval of written procedures and radiological data and reports.

16

17 (c) A description of the minimum qualifications and training programs for individuals 

18 performing radiological monitoring and those individuals in the quality 

19 assurance program.

20

21 (d) Written procedures for quality assurance activities, including activities involving 

22 sample analysis, calibration of instrumentation, calculation techniques, data 

23 evaluation, and data reporting.

24

25 (e) Quality control in the laboratory, including procedures covering statistical data 

26 evaluation, instrument calibration, duplicate sample programs, and spike sample 

27 programs. Outside laboratory quality assurance/quality control programs 

28 are included.

29

30 (f) Provisions for periodic management audits to verify that the quality assurance 

31 program is effectively implemented to verify compliance with applicable rules, 

32 regulations, and license requirements and to protect employees by maintaining 

33 effluent releases and exposures ALARA.

34

35 (2) All reporting and record keeping will be done in conformance with the criteria presented 

36 in Section 4.2.2 of this SRP. Furthermore, the applicant will maintain records used to 

37 demonstrate compliance and evaluate dose, intake, and releases until NRC terminates 

38 the license as required by 10 CFR Part 20. The radiological quality assurance programs 

39 proposed for all radiological, effluent, and environmental (including groundwater) 

40 monitoring are in accordance with Regulatory Guide 4.14, Revision 1 (NRC, 1980) and 

41 Regulatory Guide 4.15, Revision 2 (NRC, 2007).

42

43 (3) For license renewal applications, the historical radiological quality assurance program 

44 results are included through the most recent reporting period preceding the submittal of 

45 the application. The effectiveness of the historical program is adequately discussed with 

46 regard to all applicable 10 CFR Part 20 regulatory requirements. Long-term trends are 

47 discussed, any short-term deviations from the long-term trends are appropriately 

48 explained, and mitigation measures are described.

49

50
4-20

1 4.7.4 Evaluation Findings

2

3 If the staff determines that no license conditions are required for the quality assurance program 

4 because the applicant or licensee provided adequate and complete information that fully 

5 addresses all relevant regulatory requirements, typically a single paragraph is sufficient for the 

6 evaluation findings section. Begin the section with the sentence: “NRC staff has completed its 

7 review of the quality assurance program at the conventional uranium mill or heap leach facility in 

8 accordance with Section 4.7.3 of the standard review plan.” Following this statement, state 

9 what information the applicant provided in the application. As discussed in the introduction of 

10 this SRP, a bullet or sentence format may be used to list what information the applicant 

11 has provided. 

12

13 After the description of the information the applicant provided, the following or a similar 

14 statement can be added: “Based on the review conducted by NRC staff, the information 

15 provided in the application meets the applicable acceptance criteria of Section 4.7.3 of the 

16 standard review plan. Therefore, NRC staff concludes that the applicant’s quality assurance 

17 program is acceptable and is in compliance with 10 CFR 20.1101, which provides requirements 

18 for radiation protection programs.” As a concluding statement, state the reason why the 

19 applicant’s information is considered adequate and complete, and why or how that information 

20 complies with the identified regulatory requirements.

21

22 If license conditions are needed, then a more detailed discussion is typically required. Begin 

23 this section with the sentence: “NRC staff has completed its review of the quality assurance 

24 program at the conventional uranium mill or heap leach facility in accordance with Section 4.7.3 

25 of the standard review plan.” Following this statement, state what information the applicant 

26 provided in the application, including identification of the information that was omitted or 

27 inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

28 used to list what information the applicant has provided. Next, state why a license condition is 

29 needed, followed by the license condition or conditions. 

30

31 In a separate paragraph following the discussion of the required license condition(s), include the 

32 statement: “Based on the review conducted by NRC staff, the information provided in the 

33 application, supplemented by provisions of the license condition(s) discussed above, meets the 

34 applicable acceptance criteria of Section 4.7.3 of the standard review plan. Therefore, NRC 

35 staff concludes that the applicant’s quality assurance program is acceptable and is in 

36 compliance with 10 CFR 20.1101, which provides requirements for radiation protection 

37 programs.” If not discussed in the preceding paragraph(s), include a statement or summation 

38 as to why or how the application and license condition(s) jointly comply with the identified 

39 regulatory requirements.

40

41 4.7.5 References

42

43 EPA. “EPA Requirements for Quality Assurance Project Plans.” EPA QA/R–5. 

44 Washington, DC: EPA, Office of Environmental Information. 2001.

45

46 NRC. Regulatory Guide 4.15, “Quality Assurance for Radiological Monitoring Programs 

47 (Inception Through Normal Operations to License Termination)—Effluent Streams and the 

48 Environment.” Rev. 2. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2007.

49

50 –––––. Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium 

51 Mills.” Rev. 1. Washington, DC: NRC, Office of Standards Development. 1980.
5-1

1 5.0 OPERATIONAL ENVIRONMENTAL MONITORING

2

3 This section provides guidance for reviewing the operational environmental monitoring program 

4 for the proposed or existing site. Operational environmental monitoring addresses monitoring of 

5 effluents that leave the protected area and, as such, are no longer under the control of the 

6 operator. In plant occupational monitoring, which is monitoring in the protected area for the 

7 purposes of determining occupational exposure, is discussed in Section 6 of this standard 

8 review plan (SRP). Preoperational environmental monitoring, which is monitoring prior to 

9 operations, is discussed in Section 2 of this SRP.

10

11 5.1 Operational Environmental Monitoring—Surface Water

12

13 5.1.1 Areas of Review

14

15 This section provides staff review guidance on surface water monitoring during the operational 

16 phase of conventional uranium mill or heap leach facilities. Preoperational monitoring is 

17 conducted as part of site characterization, and staff review procedures and acceptance criteria

18 are given in Section 2.8 of this SRP. The applicant’s surface water operational monitoring 

19 program should allow timely detection of contaminant runoff into surface waters. The staff 

20 should review the technical bases and procedures of the applicant’s surface water operational 

21 monitoring program and the sampling locations and frequencies. For all of the aspects of 

22 surface water monitoring program that involve analysis of water samples, procedures for sample 

23 collection, sample preservation, and analysis should be reviewed. 

24

25 5.1.2 Review Procedures

26

27 The staff should use the following procedures when reviewing the operational surface water 

28 monitoring program:

29

30 (1) Review the surface water monitoring program and determine if the applicant identified 

31 the proper sampling locations, sampling frequency, and types of analysis consistent with 

32 Regulatory Guide 4.14 (NRC, 1980, Table 2). This information should meet, in part, the 

33 requirements of 10 CFR Part 40, Appendix A, Criterion 7.

34

35 (2) Ensure the license application includes a detailed discussion on procedures for 

36 monitoring surface water quality during operations. This information should meet,

37 in part, the requirements of 10 CFR 40.31(h); 10 CFR 40.32(c); 10 CFR 40.32(d);

38 10 CFR 40.41(c); and 10 CFR Part 40, Appendix A, Criterion 7.

39

40 5.1.3 Acceptance Criteria

41

42 The surface water operational monitoring program is acceptable if it meets the following criteria: 

43

44 (1) If a conventional uranium mill or heap leach facility is located adjacent to surface water 

45 bodies, the applicant establishes a surface water monitoring program, consistent with 

46 Regulatory Guide 4.14 (NRC, 1980), that will effectively detect releases of contaminants 

47 from disposal areas, including surface impoundments, into surface water bodies

48 crossing the side boundary and nearby offsite surface waters, including running or 

49 standing ephemeral and perennial surface waters. Alternatively, the applicant 

50 adequately demonstrates that the risk of contamination from conventional uranium mill
Operational Environmental Monitoring

5-2

1 or heap leach activities is negligible or that potential releases will be within limits set by 

2 the Clean Water Act (33 U.S.C. 1251 et seq.) and 10 CFR Part 20, Appendix B, effluent 

3 limits. Surface water bodies that occur within, upstream, and downstream of the facility

4 boundary will be sampled during milling or leaching operations.

5

6 (2) The surface water sampling locations (e.g., soil samples from bottom sediments and

7 floodplains, water samples near the edge (or shore) and midpoint of flowing waters, 

8 and at multiple depths in stagnant water bodies), sampling duration and frequencies

9 (e.g., monthly routine sampling as well as increased sampling frequencies in case of

10 seepage from disposal areas to nearby surface water bodies), a list of sampling 

11 radiological and nonradiological constituents, and reporting procedures are described in 

12 detail consistent with Regulatory Guide 4.14 (NRC, 1980). The application includes a 

13 sampling schedule and a map (or maps) showing preoperational monitoring, standby 

14 monitoring (if the facility is on standby, but the applicant continues the monitoring 

15 program), and operational monitoring locations in reference to disposal areas, natural 

16 surface water bodies within and in the vicinity of the facility boundary, and within 100-

17 year flood zone boundaries. Maps are clearly labeled and designate scale, orientation, 

18 and geographic coordinates. In addition to maps, the applicant provides tabular 

19 summaries of sampling locations. The sampling locations are arranged so that major 

20 upstream and downstream locations of the conventional uranium mill or heap leach 

21 facility are properly monitored. If streams are ephemeral, the applicant proposes 

22 appropriate deviations from the regular sampling program.

23

24 5.1.4 Evaluation Findings

25

26 If the staff determines that no license conditions are required for the surface water monitoring 

27 program because the applicant or licensee provided adequate and complete information that 

28 fully addresses all relevant regulatory requirements, typically a single paragraph is sufficient for 

29 the evaluation findings section. Begin the section with the sentence: “NRC staff has completed 

30 its review of the surface water monitoring program at the conventional uranium milling or heap 

31 leach facility in accordance with Section 5.1.3 of the standard review plan.” Following this 

32 sentence, state what information the applicant provided in the application. As discussed in the 

33 introduction of this SRP, a bullet or sentence format may be used to list what information the 

34 applicant has provided. 

35

36 After the description of the information the applicant provided, the following or a similar 

37 statement can be added: “Based on the review conducted by NRC staff, the information 

38 provided in the application meets the applicable acceptance criteria of Section 5.1.3 of the 

39 standard review plan. Therefore, NRC staff concludes that the applicant’s operational surface 

40 water monitoring program is acceptable and is in compliance with 10 CFR 40.31(h), which 

41 defines requirements for applications for specific licenses; 10 CFR 40.32(c), which requires the 

42 applicant’s proposed equipment, facilities, and procedures to be adequate to protect health and 

43 minimize danger to life or property; 10 CFR 40.32(d), which requires that the issuance of the 

44 license will not be inimical to the common defense and security or to the health and safety of the 

45 public; 10 CFR 40.41(c), which requires the applicant to confine source or byproduct material to 

46 the locations and purposes authorized in the license; and 10 CFR Part 40, Appendix A, 

47 Criterion 7, which requires preoperational and operational monitoring and detection programs.” 

48 As a concluding statement, indicate the reason why the applicant’s information is considered 

49 adequate and complete, and why or how that information complies with the identified 

50 regulatory requirements.
Operational Environmental Monitoring

5-3

1 If license conditions are needed, then a more detailed discussion is typically required. Begin 

2 this section with the sentence: “NRC staff has completed its review of the surface water 

3 monitoring program at the conventional uranium milling or heap leach facility in accordance with 

4 Section 5.1.3 of the standard review plan.” Following this sentence, state what information the 

5 applicant provided in the application, including identification of the information that was omitted 

6 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

7 used to list what information the applicant has provided. Next, state why a license condition is 

8 needed, followed by the license condition or conditions. 

9

10 In a separate paragraph following the discussion of the required license condition(s), include the 

11 statement: “Based on the review conducted by NRC staff, the information provided in the 

12 application, supplemented by provisions of the license condition(s) discussed above, meets the 

13 applicable acceptance criteria of Section 5.1.3 of the standard review plan. Therefore, NRC 

14 staff concludes that the applicant’s operational surface water monitoring program is acceptable 

15 and is in compliance with 10 CFR 40.31(h), which defines requirements for applications for 

16 specific licenses, 10 CFR 40.32(c), which requires the applicant’s proposed equipment, 

17 facilities, and procedures to be adequate to protect health and minimize danger to life or 

18 property; 10 CFR 40.32(d), which requires that the issuance of the license will not be inimical to 

19 the common defense and security or to the health and safety of the public; 10 CFR 40.41(c), 

20 which requires the applicant to confine source or byproduct material to the locations and 

21 purposes authorized in the license; and 10 CFR Part 40, Appendix A, Criterion 7, which requires 

22 preoperational and operational monitoring and detection programs.” If not discussed in the 

23 preceding paragraph(s), include a statement or summation as to why or how the application and 

24 license condition(s) jointly comply with the identified regulatory requirements.

25

26 5.1.5 References

27

28 NRC. Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium 

29 Mills.” Rev. 1. Washington, DC: NRC, Office of Standards Development. 1980.

30

31 5.2 Operational Environmental Monitoring—Groundwater

32

33 5.2.1 Areas of Review 

34

This section discusses monitoring groundwater quality in the uppermost aquifer1 35 during the 

36 operational phase of conventional uranium mill or heap leach activities. The groundwater 

37 operational monitoring program should ensure that leakage of hazardous contaminants from 

38 disposal areas, including surface impoundments, is detected long before process effluents and 

39 hazardous contaminants could degrade the quality of groundwater beyond the regulatory point 

40 of compliance or downstream of the facility boundary. 

41

42 The regulatory point of compliance is the location at which the groundwater is monitored to 

43 determine the compliance with the groundwater protection standards. The operational 

44 groundwater monitoring program should also allow timely implementation of corrective actions 

45 against these hazardous constituents. The point of compliance is to provide the earliest 

46 practicable warning for groundwater contamination on the hydraulically downgradient edge of 

47 the disposal area, if hazardous constituents leak from disposal areas into the groundwater. The 

48 point of compliance is a site-specific location in the uppermost aquifer and defined as the 

49 intersection of a vertical plane with the uppermost aquifer at the hydraulically downgradient limit 

 1

The definition of the uppermost aquifer is provided in Section 2.2.3 of this SRP.
Operational Environmental Monitoring

5-4

1 of the disposal area, where the groundwater protection standard must be met (10 CFR Part 40, 

2 Appendix A; NUREG–1620, NRC, 2003).

3

4 Early detection of leakage of hazardous contaminants by monitoring wells is influenced by:

5

6 • The thickness of the uppermost aquifer, local- and regional-scale groundwater flow and 

7 local-scale milling-induced disturbances (e.g., groundwater pumpage from the 

8 uppermost aquifer to meet consumptive water uses during construction and operation);

9

10 • Development of short- or long-term groundwater mounds due to leaks or accidental 

11 spills from operation sites, surface impoundments on the groundwater flow in the 

12 uppermost aquifer;

13

14 • The distance that monitoring wells are placed from disposal areas;

15

16 • The boundaries of the proposed facility;

17

18 • The well spacing;

19

20 • The frequency with which the monitoring wells are sampled; and

21

22 • The water quality parameters and chemical constituents that are sampled.

23

24 The staff should review the technical bases and procedures for the following components of the 

25 applicant’s groundwater operational monitoring program: 

26

27 • Selection of hazardous contaminants and their respective background levels, consistent 

28 with Regulatory Guide 4.14 (NRC, 1980).

29

30 • A description and technical basis for determining location of the regulatory point

31 of compliance.

32

33 • The placement of detection monitoring wells upgradient and downgradient of disposal 

34 areas, and downgradient of the facility boundary.

35

36 • If the unsaturated zone hydrology has complex infiltration patterns, applicant-proposed

37 field tests (subject to NRC approval) to verify horizontal continuity between the

38 upgradient (baseline) and downgradient wells with respect to disposal areas, and 

39 monitoring wells at or downstream of the facility boundary, and vertical isolation 

40 between the uppermost aquifer and vertical leakage monitoring wells below the 

41 uppermost aquifer.

42

43 • The leakage monitoring program, including well sampling schedules, criteria for placing

44 wells on detection status, and corrective actions to be taken in the event of detection

45 (leakage detection system in liners underlying surface impoundments are discussed in 

46 Section 3 of this SRP).

47

48 For all of the preceding aspects of the groundwater monitoring program that involve analysis of 

49 water samples, procedures for sample collection and analysis should be reviewed. 

50
Operational Environmental Monitoring

5-5

1 5.2.2 Review Procedures

2

3 Hydrogeologic and groundwater chemistry data are collected before conventional uranium mill

4 or heap leach operations commence to establish a basis for comparing with operational 

5 monitoring data. Hydrogeologic data are used to evaluate whether disposal areas, including 

6 surface impoundments, are confined and operated safely, and to confirm that monitoring wells 

7 have been located correctly. Water chemistry data are used to establish a set of water quality 

8 standards for detection monitoring and corrective action programs. The staff should determine 

9 whether these objectives of the operational monitoring program have been met. To this end, 

10 the staff should perform the following activities:

11

12 (1) Review the applicant’s proposed (or procedure for proposing) preoperational (baseline) 

13 groundwater quality parameters (in conjunction with Section 2.8.2.3, Acceptance 

14 Criterion 2 of this SRP), chemical and radioactive constituents, and the respective 

15 specified background limits for a groundwater protection standard, which will be used as 

16 indicators to enable timely detection and reporting of leakage of hazardous constituents 

17 [as described in Regulatory Guide 4.14 (NRC, 1980)] from disposal areas. Staff may 

18 refer to the procedures given in Section 2 of this SRP for establishing baseline 

19 parameters. This information should meet, in part, the requirements of 10 CFR Part 40, 

20 Appendix A, Criteria 5B(1), 5B(2), 5B(5), 5C, and 7.

21

22 (2) Verify that a point of compliance is established and properly delineated. This information 

23 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criterion 5B(1). 

24

25 (3) Review the applicant’s water sampling procedure at operational monitoring wells and the 

26 method for excluding outliers in the samples. This information should meet, in part, the 

27 requirements of 10 CFR 40.32(c). 

28

29 (4) Review the applicant’s technical basis or procedures for establishing the appropriate 

30 monitoring well spacing for vertical and horizontal leakage monitoring. This information 

31 should meet, in part, the requirements of 10 CFR Part 40, Appendix A, Criterion 7.

32

33 (5) If uncertainties and complexities exist in the hydrogeology beneath the proposed 

34 conventional uranium mill or heap leach facility, evaluate the applicant’s aquifer test 

35 procedures for groundwater monitoring in the uppermost aquifer within and downstream 

36 of the point of compliance. If the hydrogeology beneath the propose site is uniform and 

37 well-described in previous studies and publically-available reports, aquifer testing may 

38 not be necessary. Determine whether aquifer testing for groundwater monitoring is 

39 sufficient to show (i) a horizontal hydraulic connection between the uppermost aquifer 

40 beneath the site and the monitoring well network completed in the same aquifer at the 

41 downstream point of compliance and, if it exists, beyond the facility boundary, and (ii) a 

42 vertical hydraulic separation between the uppermost aquifer and underlying major 

43 aquifers, if it exists, within the facility boundary. This information should meet, in part, 

44 the requirements of 10 CFR Part 40, Appendix A, Criterion 7.

45

46 (6) Evaluate whether procedures describing the operational leakage monitoring program 

47 include sampling schedules, sampling and analytical procedures, criteria for placing the 

48 disposal areas on leakage status, and corrective action and notification procedures to be 

49 followed if leakage from the disposal areas is detected. This information should meet, in 

50 part, the requirements of 10 CFR Part 40, Appendix A, Criteria 5B(2), 5D, 5F, 7, and 13.

51
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1 5.2.3 Acceptance Criteria 

2

3 The groundwater monitoring program is acceptable if it meets the following criteria: 

4

5 (1) As discussed in Section 2.8.2.3 of this SRP, a preoperational monitoring program has 

6 been in place for 1 year and samples were taken at least monthly. However, if mills 

7 were in existence prior to groundwater compliance provisions of 10 CFR Part 40, 

8 Appendix A, background water quality may already be defined by a license condition. In 

9 either case, in accordance with developed data on the groundwater flow, potential 

10 contaminants, and site information, a license condition identifies hazardous constituents 

11 and establishes the site-specific point of compliance for the licensing period. 

12

13 Hazardous constituents that may leak from disposal areas will not exceed the 

14 NRC-approved groundwater protection standards in the uppermost aquifer beyond 

15 the point of compliance during the licensing period. The same groundwater protection 

16 standards are assigned to monitoring wells within the uppermost aquifer if baseline data 

17 indicate insignificant chemical heterogeneity. Alternatively, if individual monitoring 

18 wells in the uppermost aquifer exhibit unique baseline water quality, the groundwater 

19 protection standards are assigned on a well-by-well basis. If the groundwater protection 

20 standards vary at monitoring wells, a table is included listing monitoring wells and their 

21 respective standards.

22

23 The applicant commits to establishing limits for hazardous constituents at the point 

24 of compliance, such that the concentration of a hazardous constituent will 

25 not exceed either:

26

27 (a) The NRC-approved background concentration of that constituent in groundwater.

28

29 (b) The respective maximum contaminant level contained in 10 CFR Part 40,

30 Appendix A, Criterion 5C.

31

32 (c) An NRC-approved alternative concentration limit (ACL). The Commission 

33 may establish a site-specific ACL for a hazardous constituent as provided in 

34 10 CFR Part 40, Appendix A, Criterion 5B(5) if it finds that the proposed limit is 

35 as low as is reasonably achievable (ALARA), after considering practicable 

36 corrective actions, and that the constituent will not pose a substantial present or 

37 potential hazard to human health or the environment as long as the ACL is not 

38 exceeded. See 10 CFR Part 40, Appendix A, Criterion 5B(6). ACLs are to be 

39 requested as part of a license amendment application. 

40

41 (2) A site-specific point of compliance is established to provide the earliest practicable 

42 warning for groundwater contamination on the hydraulically downgradient edge of the 

43 disposal area, if hazardous constituents leak from disposal areas into the groundwater. 

44 The established point of compliance is consistent with the definition in 10 CFR Part 40, 

45 Appendix A. 

46

47 (3) The applicant uses an appropriate water sampling procedure and method for excluding 

48 outliers in the samples. The applicant provides a reference for outlier elimination. 

49 Outliers are not eliminated if the applicant demonstrates that the concentration is in 

50 natural variation. 

51
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1 (4) The applicant establishes criteria for determining monitoring well locations and spacing. 

2

3 (a) Horizontal Monitoring Well Spacing. Monitoring wells between the point of 

4 compliance and the downgradient facility boundary are used to detect horizontal 

5 migration of hazardous constituents beyond the point of compliance. These 

6 monitoring wells generally surround the entire disposal area and are screened

7 through the entire saturated thickness of the uppermost aquifer to maximize the 

8 likelihood of leakage detection. The applicant has some discretion in determining 

9 the appropriate distance of horizontal monitoring wells from disposal areas, but 

10 provides justification for well spacing in the application. For example, the 

11 applicant can use rigorous geochemical, flow, and contaminant transport models 

12 to demonstrate that theoretical leakage can be detected and controlled at the 

13 monitoring well locations within 60 days of leakage. In determining the 

14 appropriate spacing between perimeter monitoring wells, the applicant considers

15 such factors as the distance of the monitoring wells from the edge of disposal 

16 areas; the size of disposal areas; groundwater flow directions and velocities 

17 beneath the facility; and the potential for mixing, dispersion, sorption, and 

18 chemical reactions.

19

20 (b) Vertical Monitoring Well Spacing. Vertical monitoring wells at the point of 

21 compliance are used to detect vertical leakage from the uppermost aquifer into

22 the underlying major aquifers (used as drinking, livestock, or agricultural supplies 

23 by local people within and nearby the facility boundary), if they exist. The 

24 applicant considers the thickness, continuity, and vertical conductivity of the 

25 confining layer below the uppermost aquifer, the vertical hydraulic gradient 

26 across the confining layer, and hydraulic properties of the underlying major 

27 aquifers in determining the number, location, depth, and spacing of vertical 

28 monitoring wells. Well spacing and placement for vertical leakage monitoring 

29 wells should be supported by technical analyses, such as calculations and 

30 modeling. Monitoring well placement should also account for geologic 

31 (e.g., fractures, joints, faults) or artificial features (e.g., exploratory holes, 

32 improperly abandoned water or oil wells, abandoned open pits) that could affect 

33 groundwater flow in the uppermost aquifer and underlying major aquifers. The 

34 appropriate number of these monitoring wells varies from site to site. It might be

35 appropriate to exclude the requirement to monitor water quality in the underlying 

36 aquifer if (i) the underlying aquifer is a poor producer of water, (ii) the underlying 

37 aquifer is of poor water quality (i.e., not suitable for any consumption or 

38 irrigation), or (iii) there is a large and effective confining layer (aquitard) between 

39 the uppermost aquifer and the underlying major aquifer.

40

41 (5) The applicant establishes aquifer test procedures for groundwater monitoring. However, 

42 if the hydrogeology beneath the proposed site is uniform and well-described in previous 

43 studies and publically-available reports, aquifer testing may not be necessary. 

44 Monitoring wells will be tested to establish (i) the hydraulic connection between the 

45 uppermost aquifer beneath the facility and monitoring wells placed in the same aquifer 

46 within and beyond the facility boundary and (ii) vertical hydraulic separation between the 

47 uppermost aquifer and the vertical leakage monitoring wells placed below the uppermost 

48 aquifer. Once a monitoring well is installed, it should be tested for hydraulic connection

49 between the uppermost aquifer beneath the disposal areas and horizontal monitoring 

50 wells within and beyond the facility boundary. Moreover, there should be vertical 

51 isolation between the uppermost aquifer and vertical leakage monitoring wells, if 
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1 required, below the uppermost aquifer. Such testing will confirm monitoring system 

2 performance and will verify the validity of the site conceptual model reviewed in 

3 Section 2 of this SRP. The field test approaches (e.g., aquifer pumping tests, slug tests)

4 the applicant proposed should have sound technical bases. For example, if aquifer 

5 pump testing is chosen, the test approaches typically consist of a pumping test that 

6 subjects the pumping well to a sustained maximum withdrawal rate while monitoring the 

7 horizontal and vertical leakage monitoring wells for drawdown. The test should continue 

8 until the effects of pumping can be clearly seen via drawdown at the monitoring wells. 

9 To investigate vertical confinement or hydraulic isolation between the uppermost aquifer 

10 and underlying major aquifers, if they exist, water levels in the uppermost and underlying 

11 aquifers may also be monitored during the pumping tests.

12

13 (6) The applicant defines operational approaches for the monitoring program. 

14

15 (a) The monitoring program indicates those wells that will be monitored for 

16 hazardous constituent concentration levels included in the NRC-approved 

17 groundwater protection standards (as specified by 10 CFR Part 40, Appendix A, 

18 Criteria 5D and 13), the monitoring frequency, and the criteria for determining 

19 when leakage has occurred. 10 CFR Part 40, Appendix A, Criterion 13 includes 

20 a list of hazardous constituents for which standards must be set and complied 

21 with, if the specific constituents are reasonably expected to be in or derived from 

22 the byproduct material and have been detected in groundwater in the uppermost 

23 aquifer. As discussed in Section 2.8.2.3 of this SRP, if a new constituent is 

24 detected during operational monitoring and is excluded from the set of baseline 

25 constituents, the applicant commits to providing the technical justification for its

26 exclusion. NRC has flexibility to add other constituents not identified in 

27 Criterion 13 on a case-by-case basis, but such additions must be based on 

28 a sound technical and regulatory basis. If necessary, new constituents will

29 be added in a timely manner if a corrective action plan is required following 

30 detection of a leak, either when the corrective action plan is accepted for 

31 review or at some time during the lifetime of the corrective action program

32 (NUREG–1620, NRC, 2003). 

33

34 An acceptable leakage monitoring program indicates that monitoring wells will 

35 be sampled for hazardous constituent concentrations at least every 2 weeks 

36 during conventional uranium mill or heap leach operations. Criteria for 

37 determining leakage are discussed in Acceptance Criterion 1 of this section. 

38 The applicant commits to obtaining a verification sample within 48 hours after 

39 results of the first analyses are received. If the second sample does not indicate 

40 that NRC-approved groundwater protection standards were exceeded, then a 

41 third sample will be taken within 48 hours after the second set of sampling data 

42 was acquired. If neither the second nor the third sample indicates that 

43 groundwater protection standards are exceeded, then the first sample is 

44 considered in error and the well is removed from leakage status. If either the 

45 second or third sample contains hazardous constituents exceeding groundwater 

46 protection standards, then leakage is confirmed, the monitoring well is placed in 

47 leakage status, and corrective action is initiated.

48

49 (b) The leakage monitoring operational procedures also include corrective action 

50 and notification plans in the event of leakage. As recommended, NRC will be 

51 notified within 24 hours by telephone or e-mail and within 7 days in writing from 
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1 the time leakage is verified. A written report describing the leakage event,

2 proposed corrective action program, and supporting rationale for NRC approval

3 prior to putting the program into operation unless otherwise directed by NRC 

4 must be submitted to NRC within 60 days of the detection confirmation. 

5

6 In the event of leakage, the corrective action program will be implemented to 

7 alleviate conditions that lead to excessive seepage impacts and restore 

8 groundwater quality as soon as possible and, in no event, later than 18 months 

9 after NRC has been notified that the groundwater protection standards have 

10 been exceeded. The corrective action program will address removing or 

11 treating-in-place hazardous constituents between the point of compliance and the 

12 downgradient facility boundary and return the hazardous concentration levels to 

13 the concentration limits set as groundwater protection standards. The corrective 

14 action plan should consider whether the ALARA analysis and target 

15 concentration levels may be reasonably attained by practicable corrective actions 

16 (NRC, 2003). NRC will determine when the licensee may terminate the 

17 corrective action operations based on field data from the monitoring program and 

18 other information that provides reasonable assurance that NRC-approved site19 specific groundwater protection standards are met.

20

21 5.2.4 Evaluation Findings

22

23 If the staff determines that no license conditions are required for the groundwater monitoring 

24 program because the applicant or licensee provided adequate and complete information that 

25 fully addresses all relevant regulatory requirements, typically a single paragraph is sufficient for 

26 the evaluation findings section. Begin the section with the sentence: “NRC staff has completed 

27 its review of the groundwater monitoring program at the conventional uranium milling or heap 

28 leach facility in accordance with Section 5.2.3 of the standard review plan.” Following this 

29 sentence, state what information the applicant provided in the application. As discussed in the 

30 introduction of this SRP, a bullet or sentence format may be used to list what information the 

31 applicant has provided. 

32

33 After the description of the information the applicant provided, the following or a similar 

34 statement can be added: “Based on the review conducted by NRC staff, the information 

35 provided in the application meets the applicable acceptance criteria of Section 5.2.3 of the 

36 standard review plan. Therefore, NRC staff concludes that the applicant’s operational 

37 groundwater monitoring program is acceptable and is in compliance with 10 CFR 40.32(c), 

38 which requires that proposed equipment, facilities and procedures be adequate to protect health 

39 and minimize danger to life or property; 10 CFR Part 40, Appendix A, Criterion 5B(1), which 

40 requires applicants to prevent hazardous constituents from exceeding concentration limits 

41 in the uppermost aquifer beyond the point of compliance; 10 CFR Part 40, Appendix A, 

42 Criterion 5B(2), which provides criteria for chemical constituents to be considered as a 

43 hazardous constituent subject to 5B(5); 10 CFR Part 40, Appendix A, Criterion 5B(5), which 

44 requires applicants to ensure that hazardous constituents at the point of compliance do not 

45 exceed the background concentration; and 10 CFR Part 40, Appendix A, Criterion 5C, which 

46 provide concentration limits for contaminants; 10 CFR Part 40, Appendix A, Criterion 5D, which 

47 requires a groundwater corrective action program; 10 CFR Part 40, Appendix A, Criterion 5F, 

48 which requires action to be taken to alleviate seepage impacts where they are occurring and 

49 restore groundwater quality; 10 CFR Part 40, Appendix A, Criterion 7, which requires 

50 groundwater compliance monitoring programs; and 10 CFR Part 40, Appendix A, Criterion 13, 

51 which requires that groundwater protection standards need to be established for constituents 
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1 reasonably expected to be in or derived from byproduct materials and detected in groundwater 

2 in the uppermost aquifer.” As a concluding statement, indicate the reason why the applicant’s 

3 information is considered adequate and complete, and why or how that information complies 

4 with the identified regulatory requirements.

5

6 If license conditions are needed, then a more detailed discussion is typically required. Begin 

7 this section with the sentence: “NRC staff has completed its review of the groundwater 

8 monitoring program at the conventional uranium mill or heap leach facility in accordance with 

9 Section 5.2.3 of the standard review plan.” Following this sentence, state what information the 

10 applicant provided in the application, including identification of the information that was omitted 

11 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

12 used to list what information the applicant has provided. Next, state why a license condition is 

13 needed, followed by the license condition or conditions. 

14

15 In a separate paragraph following the discussion of the required license condition(s), include the 

16 statement: “Based on the review conducted by NRC staff, the information provided in the 

17 application, supplemented by provisions of the license condition(s) discussed above, meets the 

18 applicable acceptance criteria of Section 5.2.3 of the standard review plan. Therefore, NRC 

19 staff concludes that the applicant’s operational groundwater monitoring program is acceptable 

20 and is in compliance with 10 CFR 40.32(c), which requires that proposed equipment, 

21 facilities and procedures be adequate to protect health and minimize danger to life or property;

22 10 CFR Part 40, Appendix A, Criterion 5B(1), which requires applicants to prevent hazardous 

23 constituents from exceeding concentration limits in the uppermost aquifer beyond the point of 

24 compliance; 10 CFR Part 40, Appendix A, Criterion 5B(2), which provides criteria for chemical 

25 constituents to be considered as a hazardous constituent subject to 5B(5); 10 CFR Part 40, 

26 Appendix A, Criterion 5B(5), which requires applicants to ensure that hazardous constituents at 

27 the point of compliance do not exceed the background concentration; and 10 CFR Part 40, 

28 Appendix A, Criterion 5C, which provide concentration limits for contaminants; 10 CFR Part 40, 

29 Appendix A, Criterion 5D, which requires a groundwater corrective action program;

30 10 CFR Part 40, Appendix A, Criterion 5F, which requires action to be taken to alleviate 

31 seepage impacts where they are occurring and restore groundwater quality; 10 CFR Part 40, 

32 Appendix A, Criterion 7, which requires groundwater compliance monitoring programs; and 10

33 CFR Part 40, Appendix A, Criterion 13, which requires that groundwater protection standards 

34 need to be established for constituents reasonably expected to be in or derived from byproduct 

35 materials and detected in groundwater in the uppermost aquifer.” If not discussed in the 

36 preceding paragraph(s), include a statement or summation as to why or how the application and 

37 license condition(s) jointly comply with the identified regulatory requirements.

38

39 5.2.5 References

40

41 NRC. NUREG–1620, “Standard Review Plan for the Review of a Reclamation Plan for Mill 

42 Tailings Sites Under Title II of the Uranium Mill Tailings Radiation Control Act of 1978.” Rev. 1. 

43 Washington, DC: NRC. June 2003.

44

45 NRC. Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium 

46 Mills.” Rev. 1. Washington, DC: NRC, Office of Standards Development. 1980.

47

48
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1 5.3 Operational Airborne Monitoring

2

3 Operational airborne monitoring pertains to monitoring of airborne effluents that leave the 

4 protected area and, as such, are no longer under the control of the operator. The purpose of 

5 operational air monitoring is to verify compliance with public dose limits. Procedures for review 

6 of workplace air monitoring, which is air monitoring in the protected area to verify compliance 

7 with occupational dose limits, are provided in Section 6 of this SRP. Procedures for review of 

8 preoperational air monitoring, which is monitoring of air prior to operations, are provided in 

9 Section 2 of this SRP.

10

11 5.3.1 Areas of Review 

12

13 The staff should review the effluent verification program proposed for assessing concentrations 

14 and quantities of radioactive materials released to the unrestricted area surrounding the facility. 

15 The staff should review the following areas:

16

17 • Technical bases proposed for determining radionuclide concentrations for demonstrating 

18 compliance with standards;

19

20 • Frequency of sampling and analysis;

21

22 • The types and sensitivity of analysis;

23

24 • Action levels and corrective action requirements;

25

26 • Minimum number and criteria for locating monitoring stations; and

27

28 • Commitments for semiannual effluent and environmental monitoring reporting.

29

30 5.3.2 Review Procedures 

31

32 Staff should use the following procedures when reviewing the airborne radiation 

33 monitoring program:

34

35 (1) Verify that the applicant provided sufficient information regarding estimated public doses 

36 and that those doses are consistent with the ALARA requirements described in 

37 Regulatory Guide 8.37, “ALARA Levels for Effluents from Materials Facilities” (NRC, 

38 1993). Furthermore, review the type of verification program the applicant proposes. If 

39 calculations are proposed to demonstrate compliance, ensure that the applicant agrees 

40 to perform effluent monitoring to confirm the licensing basis and the validity of 

41 calculations used for estimating effluent concentrations and calculating dose. This 

42 information should meet, in part, the requirements of 10 CFR 20.1101; 10 CFR 20.1301; 

43 10 CFR 20.1302; 10 CFR 20.1501; and 10 CFR Part 40, Appendix A, Criterion 8.

44

45 (2) Determine whether the proposed locations of the airborne effluent monitoring stations 

46 are consistent with guidance in Regulatory Guide 4.14, “Radiological Effluent and 

47 Environmental Monitoring at Uranium Mills,” Revision 1 (NRC, 1980) if an effluent 

48 monitoring program is proposed. This information should meet, in part, the requirements 

49 of 10 CFR 20.1501.

50
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1 (3) Verify that the applicant commits to, at a minimum, semiannual airborne effluent 

2 reporting. This information should meet, in part, the requirements of 10 CFR 40.65.

3

4 (4) Confirm that the applicant provides a drawing that depicts the location of environmental 

5 air samplers and provides a basis for the location of the samplers. This information 

6 should meet, in part, the requirements of 10 CFR 20.1501 and 10 CFR Part 40, 

7 Appendix A, Criterion 8.

8

9 (5) Verify that monitoring equipment is identified by type, sensitivity, calibration methods and 

10 frequency, availability, range of sensitivity, and planned use to accurately measure 

11 concentrations of airborne radioactive species. This information should meet, in part, 

12 the requirements of 10 CFR 20.1501.

13

14 (6) Verify that the applicant uses appropriate techniques to measure airborne uranium, 

15 Ra-226, and Th-230. This information should meet, in part, the requirements of 

16 10 CFR 20.1101 and 10 CFR 20.1701.

17

18 (7) Verify that the historical airborne effluent monitoring program and the airborne radiation 

19 monitoring program results are included through the most recent reporting period 

20 preceding application submittal for license renewal applications. This information should 

21 meet, in part, the requirements of 10 CFR 20.1101.

22

23 5.3.3 Acceptance Criteria

24

25 The airborne radiation monitoring program is acceptable if it meets the following criteria: 

26

27 (1) The program:

28

29 • Provides data to analyze maximum public exposure in accordance with 

30 10 CFR 20.1301 and 10 CFR 20.1302;

31

32 • Provides data to report airborne effluents in accordance with 10 CFR 40.65 

33 (i.e., at the boundary of unrestricted areas);

34

35 • Uses airborne effluent monitoring programs to evaluate both point (e.g., a 

36 defined stack or pipe) and diffuse (e.g., loose surface contamination escaping the 

37 uranium recovery facility) sources; and

38

39 • Performs airborne effluent monitoring consistent with guidance so that the 

40 applicant can confirm the licensing basis and the validity of calculations used for 

41 estimating effluent concentrations and calculating dose, if the applicant proposes 

42 calculations to demonstrate compliance with 10 CFR 20.1101, 10 CFR 20.1301,

43 10 CFR 20.1302, and 10 CFR 20.1501.

44

45 (2) If the applicant proposes airborne monitoring, the proposed locations of the monitoring 

46 stations are presented and are consistent with guidance in Regulatory Guide 4.14, 

47 Revision 1 (NRC, 1980). The proposed airborne monitoring program samples radon and 

48 air particulates in accordance with Regulatory Guide 4.14, Revision 1 (NRC, 1980), and 

49 air samples to be analyzed for Rn-222 will not be composited and will be analyzed 
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1 quickly enough to minimize decay losses. The criteria used in selecting sampling 

2 locations are provided. 

3

4 (3) The applicant commits to, at a minimum, semiannual airborne monitoring reporting. 

5 These reports will be submitted to the appropriate NRC Regional Office with copies to 

6 the chief, Uranium Recovery Licensing Branch, and the project manager. Reports will 

7 specify the quantity of each of the principal radionuclides released to unrestricted areas 

8 in liquid and gaseous effluents during the previous 6 months. The process rate and 

9 pressure data are to be reported as monthly averages. A license condition will be 

10 imposed to specify these reporting requirements. 

11

12 (4) The applicant provides a drawing that depicts the location of environmental air samplers. 

13 Locations are based, in part, on a determination of general environmental airflow 

14 patterns and are consistent with Regulatory Guide 4.14, Revision 1 (NRC, 1980).

15

16 (5) Monitoring equipment is identified by type, sensitivity, calibration methods and 

17 frequency, availability, and planned use to accurately measure concentrations of 

18 airborne radioactive species. The application also demonstrates that the ranges of 

19 sensitivity are appropriate for the facility operation. 

20

21 (6) The applicant uses appropriate techniques to measure uranium in air. If Ra-226 and 

22 Th-230 may also be present in the air, additional characterization of the radionuclides in 

23 the sample is provided because gross alpha counting alone will not be able to 

24 differentiate specific radionuclides.

25

26 (7) For license renewal applications, the historical airborne effluent and airborne radiation 

27 monitoring program results are included through the most recent reporting period 

28 preceding application submittal. The effectiveness of the historical program is discussed 

29 with regard to all applicable regulatory requirements. Long-term trends are discussed, 

30 and any short-term deviations from the long-term trends are explained.

31

32 5.3.4 Evaluation Findings 

33

34 If the staff determines that no license conditions are required for the airborne radiation 

35 monitoring program because the applicant or licensee provided adequate and complete 

36 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

37 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

38 has completed its review of the airborne radiation monitoring program at the conventional 

39 uranium mill or heap leach facility in accordance with Section 5.2.3 of the standard review plan.” 

40 Following this sentence, state what information the applicant provided in the application. As 

41 discussed in the introduction of this SRP, a bullet or sentence format may be used to list what

42 information the applicant has provided. 

43

44 After the description of the information the applicant provided, the following or a similar 

45 statement can be added: “Based on the review conducted by NRC staff, the information 

46 provided in the application meets the applicable acceptance criteria of Section 5.2.3 of the 

47 standard review plan. Therefore, NRC staff concludes that the applicant’s airborne radiation 

48 monitoring program is acceptable and is in compliance with 10 CFR 20.1101, which defines the 

49 radiation protection program and ALARA requirements; 10 CFR 20.1301, which provides dose 

50 limits to members of the public; 10 CFR 20.1302, which requires monitoring to ensure 

51 compliance with dose limits to members of the public; 10 CFR 20.1501, which requires surveys 
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1 and monitoring; 10 CFR 20.1701, which requires use of process or engineering controls; 

2 10 CFR 40.65, which requires reports of effluent monitoring; and 10 CFR Part 40, Appendix A, 

3 Criterion 8, which provides requirements for control of airborne effluents.” As a concluding 

4 statement, indicate the reason why the applicant’s information is considered adequate and 

5 complete, and why or how that information complies with the identified regulatory requirements.

6

7 If license conditions are needed, then a more detailed discussion is typically required. Begin 

8 this section with the sentence: “NRC staff has completed its review of the airborne radiation 

9 monitoring program at the conventional uranium mill or heap leach facility in accordance with 

10 Section 5.2.3 of the standard review plan.” Following this sentence, state what information 

11 the applicant provided in the application, including identification of the information that was 

12 omitted or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format 

13 may be used to list what information the applicant has provided. Next, state why a license 

14 condition is needed, followed by the license condition or conditions. 

15

16 In a separate paragraph following the discussion of the required license condition(s), include the 

17 statement: “Based on the review conducted by NRC staff, the information provided in the 

18 application, supplemented by provisions of the license condition(s) discussed above, meets the 

19 applicable acceptance criteria of Section 5.2.3 of the standard review plan. Therefore, NRC 

20 staff concludes that the applicant’s airborne radiation monitoring program is acceptable and is 

21 in compliance with 10 CFR 20.1101, which defines the radiation protection program and 

22 ALARA requirements; 10 CFR 20.1301, which provides dose limits to members of the public; 

23 10 CFR 20.1302, which requires monitoring to ensure compliance with dose limits to members 

24 of the public; 10 CFR 20.1501, which requires surveys and monitoring; 10 CFR 20.1701, which 

25 requires use of process or engineering controls; 10 CFR 40.65, which requires reports of 

26 effluent monitoring; and 10 CFR Part 40, Appendix A, Criterion 8, which provides requirements 

27 for control of airborne effluents.” If not discussed in the preceding paragraph(s), include a 

28 statement or summation as to why or how the application and license condition(s) jointly comply 

29 with the identified regulatory requirements.

30

31 5.3.5 References

32

33 NRC. Regulatory Guide 8.37, “ALARA Levels for Effluents from Materials Facilities.” 

34 Washington, DC: NRC, Office of Nuclear Regulatory Research. 1993. 

35

36 –––––. Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium 

37 Mills.” Rev. 1. Washington, DC: NRC, Office of Standards Development. 1980.

38

39 5.4 Other Operational Monitoring

40

41 5.4.1 Areas of Review 

42

43 An acceptable operational monitoring program exclusive of water and air sampling includes: 

44 (i) sampling of animals, vegetation, and fish; (ii) soil and sediment sampling; (iii) direct radiation 

45 measurements; and in some instances; and (iv) radon flux. The staff should review plans for 

46 performing sampling of animals, crops, vegetation, fish, soils, and sediments that could exhibit 

47 elevated levels of radioactivity from exposure to radioactive effluents during operation and the 

48 procedures proposed for collecting the samples. The staff should review plans for performing 

49 direct radiation measurements. Staff should also review preoperational sampling data and 

50
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1 procedures to determine whether plans for operational sampling are consistent with 

2 preoperational sampling and procedures.

3

4 The staff should examine site-specific preoperational radiological data provided in the 

5 application including the results of measurements of radioactive materials occurring in important 

6 animals, crops, vegetation, fish, soils, and sediment that could be affected by the proposed 

7 operations. The staff should examine the design of the operational monitoring program, 

8 including which radionuclides are analyzed, sampling locations, sample type, sampling 

9 frequency, location and density of monitoring stations, and the detection limits for consistency 

10 with preoperational sampling.

11

12 The operational monitoring program should be consistent with the recommendations in 

13 Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium Mills,” 

14 Revision 1 (NRC, 1980) unless a justification for another sampling approach is provided. The 

15 schedule for obtaining some samples should account for seasonal availability and access to a 

16 particular area. Vegetation, food, and fish samples should be collected where a significant 

17 pathway to humans is identified in individual licensing cases.

18

19 5.4.2 Review Procedures

20

21 The staff should review the operational monitoring program, including sampling frequency, 

22 sampling methods, and sampling location and density, and exclusive of water and air sampling,

23 in accordance with the operational monitoring guidance provided in Regulatory Guide 4.14 

24 (NRC, 1980, Section 1.2). The staff should also confirm that air monitoring stations are 

25 located in a manner consistent with the principal wind directions reviewed in Section 2.3 of 

26 this SRP. The information reviewed in this procedure should meet, in part, the requirements of 

27 10 CFR Part 40, Appendix A, Criterion 7.

28

29 The staff should examine data from the operational monitoring program, paying particular 

30 attention to the design of the monitoring program, the radionuclides monitored, and the 

31 detection limits reported for each radionuclide in each sample medium. The staff should 

32 compare and contrast the operational monitoring program as implemented against the guidance 

33 provided in Regulatory Guide 4.14 (NRC, 1980). 

34

35 5.4.3 Acceptance Criteria

36

37 The operational monitoring program exclusive of water and air sampling, including sampling 

38 frequency, sampling methods, and sampling location and density is acceptable if it is 

39 established in accordance with operational monitoring guidance provided in Regulatory 

40 Guide 4.14 (NRC, 1980, Section 2.1), which describes the following types of samples that 

41 should be obtained:

42

43 (a) Animals, crops, vegetation, and fish;

44

45 (b) Soil;

46

47 (c) Sediment; and

48

49 (d) Direct radiation measurements.

50

51
Operational Environmental Monitoring

5-16

1 Descriptions of the various types of sampling are as follows.

2

3 Animals, Crops, Vegetation, and Fish Sampling. Where a significant pathway to 

4 humans is identified in individual licensing cases, animals, vegetation, crops, and fish 

5 (edible portion) samples are collected. Crops and forage vegetation are sampled at 

6 least three times during the grazing season in grazing areas in three different sectors 

7 having the highest predicted airborne radionuclide concentration due to conventional 

8 uranium mill or heap leach operations. At least three samples are collected at the time 

9 of harvest or slaughter or removal of animals from grazing for each type of crop 

10 (including vegetable gardens) or livestock raised within 3 km [1.9 mi] of the conventional 

11 uranium mill or heap leach site. Fish samples are collected semiannually from bodies of 

12 water that may be subject to seepage or surface drainage from potentially contaminated 

13 areas. Animal, crop, vegetation, and fish samples are analyzed for Ra-226 and Pb-210.

14

15 Soil Sampling. Surface soil samples are collected annually using a consistent technique 

16 at each of the locations chosen for air particulate samples. Soil samples are analyzed 

17 for natural uranium, Ra-226, and Pb-210. Section 2.8.1.3 of this SRP provides 

18 additional details on appropriate soil sampling techniques.

19

20 Sediment Sampling. Sediment samples are collected annually from surface-water 

21 locations. Sediment samples are analyzed for natural uranium, Th-230, Ra-226, and 

22 Pb-210. Section 2.8.1.3 of this SRP provides additional details on appropriate sediment 

23 sampling techniques.

24

25 Direct Radiation Measurements. Gamma exposure rates (direct radiation 

26 measurements) are measured quarterly at the sites chosen for air particulate samples. 

27 Gamma exposure rate measurements are made with passive integrating devices 

28 (such as thermoluminescence or optically stimulated luminescence dosimeters), 

29 pressurized ionization chambers, or properly calibrated portable survey instruments. 

30 Direct radiation measurements using instruments are only made in dry weather and not 

31 during periods following rainfall or when the soil is abnormally wet. Alternative direct 

32 radiation measurements are justified. Section 2.8.1.3 of this SRP provides additional 

33 details on appropriate direct radiation measurement techniques.

34

35 5.4.4 Evaluation Findings

36

37 If the staff determines that no license conditions are required for the operational monitoring 

38 program excluding water and air sampling because the applicant or licensee provided adequate 

39 and complete information that fully addresses all relevant regulatory requirements, typically a 

40 single paragraph is sufficient for the evaluation findings section. Begin the section with the 

41 sentence: “NRC staff has completed its review of the operational monitoring program excluding 

42 water and air sampling at the conventional uranium mill or heap leach facility in accordance with 

43 Section 5.4.3 of the standard review plan.” Following this sentence, state what information the 

44 applicant provided in the application. As discussed in the introduction of this SRP, a bullet or 

45 sentence format may be used to list what information the applicant has provided. 

46

47 After the description of the information the applicant provided, the following or a similar 

48 statement can be added: “Based on the review conducted by NRC staff, the information 

49 provided in the application meets the applicable acceptance criteria of Section 5.4.3 of the 

50 standard review plan. Therefore, NRC staff concludes that the applicant’s operational 

51 monitoring program excluding water and air sampling is acceptable and is in compliance with 
Operational Environmental Monitoring

5-17

1 10 CFR Part 40, Appendix A, Criterion 7, which requires operational monitoring programs.” As 

2 a concluding statement, indicate the reason why the applicant’s information is considered 

3 adequate and complete, and why or how that information complies with the identified 

4 regulatory requirements.

5

6 If license conditions are needed, then a more detailed discussion is typically required. Begin 

7 this section with the sentence: “NRC staff has completed its review of the operational 

8 monitoring program excluding water and air sampling at the conventional uranium mill or heap 

9 leach facility in accordance with Section 5.4.3 of the standard review plan.” Following this 

10 sentence, state what information the applicant provided in the application, including 

11 identification of the information that was omitted or inadequate. As discussed in the introduction 

12 of this SRP, a bullet or sentence format may be used to list what information the applicant has 

13 provided. Next, state why a license condition is needed, followed by the license condition 

14 or conditions. 

15

16 In a separate paragraph following the discussion of the required license condition(s), include the 

17 statement: “Based on the review conducted by NRC staff, the information provided in the 

18 application, supplemented by provisions of the license condition(s) discussed above, meets the 

19 applicable acceptance criteria of Section 5.4.3 of the standard review plan. Therefore, NRC 

20 staff concludes that the applicant’s operational monitoring program excluding water and air 

21 sampling is acceptable and is in compliance with 10 CFR Part 40, Appendix A, Criterion 7, 

22 which requires operational monitoring programs.” If not discussed in the preceding 

23 paragraph(s), include a statement or summation as to why or how the application and license 

24 condition(s) jointly comply with the identified regulatory requirements.

25

26 5.4.5 Reference

27

28 NRC. Regulatory Guide 4.14, “Radiological Effluent and Environmental Monitoring at Uranium 

29 Mills.” Rev. 1. Washington, DC: NRC, Office of Standards Development. 1980.

6-1

1 6.0 RADIATION SAFETY CONTROLS AND MONITORING

2

3 6.1 External Radiation Exposure Monitoring Program 

4

5 6.1.1 Areas of Review 

6

7 The staff should review survey methods, instrumentation, and equipment for determining 

8 exposures of employees to external radiation during routine and nonroutine operations, 

9 maintenance, and cleanup activities. This review should include the types of surveys 

10 conducted, criteria for determining survey locations, frequency of surveys, action levels, 

11 management audits, and corrective action requirements. Staff should also review the program 

12 for personnel exposure monitoring, the criteria for including workers in the program, the 

13 sensitivity and range of devices used, and calibration frequency and methods. 

14

15 6.1.2 Review Procedures

16

17 Staff should use the following procedures when reviewing the external radiation exposure 

18 monitoring program:

19

20 (1) Verify that the application depicts the facility layout and the location of monitors for 

21 external radiation and that the criteria for determining the external radiation monitor 

22 locations during operation are consistent with Regulatory Guide 8.30, “Health Physics 

23 Surveys in Uranium Recovery Facilities,” Revision 1 (NRC, 2002a, Sections 2.4 and 

24 2.8). This information should meet, in part, the requirements of 10 CFR 20.1101(d),

25 10 CFR 20.1201(a), and 10 CFR 20.1501.

26

27 (2) Determine that the application provides criteria to be used in identifying those employees 

28 who are to receive external exposure monitoring and that these criteria are consistent 

29 with Regulatory Guide 8.34, “Monitoring Criteria and Methods To Calculate Occupational 

30 Radiation Doses” (NRC, 1992, Section C). This information should meet, in part, the 

31 requirements of 10 CFR 20.1502.

32

33 (3) Verify that the applicant describes the proposed monitoring equipment. This information 

34 should meet, in part, the requirements of 10 CFR 20.1501.

35

36 (4) Verify that plans for documenting radiation exposures meet the requirements of 

37 10 CFR 20.2106. Verify that expected doses will be below regulatory limits in 

38 10 CFR Part 20 and will be as low as is reasonably achievable (ALARA).

39

40 (5) Ensure that the applicant’s monitoring program is adequate to protect workers from the 

41 hazards of beta radiation (skin, extremity, lens of eye) resulting from the decay products 

42 of U-238 when effective shielding is not present (e.g., maintenance operations) and is 

43 consistent with Regulatory Guide 8.30, Revision 1 (NRC, 2002a). This information 

44 should meet, in part, the requirements of 10 CFR 20.1201.

45

46 (6) Verify that the monitoring program is sufficient to detect and control gamma radiation 

47 from uranium decay products in areas where large volumes of uranium may be present 

48 (e.g., processing tanks, yellowcake storage areas) and is consistent with Regulatory 

49 Guide 8.30, Revision 1 (NRC, 2002a). This information should meet, in part, the 

50 requirements of 10 CFR 20.1501.
Radiation Safety Controls and Monitoring

6-2

1 (7) Verify that the program for external exposure monitoring and determining doses from 

2 external exposure is consistent with Regulatory Guide 8.34 (NRC, 1992, Section C). 

3 This information should meet, in part, the requirements of 10 CFR 20.1501.

4

5 6.1.3 Acceptance Criteria 

6

7 The external radiation exposure monitoring program is acceptable if it meets the 

8 following criteria: 

9

10 (1) The application contains one or more drawings that depict the facility layout and the 

11 location of monitors for external radiation during operation. Criteria for determining the 

12 external radiation monitoring locations are consistent with Regulatory Guide 8.30, 

13 Revision 1 (NRC, 2002a, Sections 2.4 and 2.8). The applicant has provided criteria for 

14 changing monitoring locations.

15

16 (2) The application provides criteria used to establish which employees will receive 

17 external exposure monitoring. These criteria are consistent with Regulatory Guide 8.34 

18 (NRC, 1992, Section C). The determination of which workers will be monitored is

19 based on an evaluation of the likely annual occupational dose a worker receives. In 

20 some cases, a category of workers for monitoring will be established if these workers 

21 are exposed to similar radiological conditions. If the radiation exposure conditions 

22 for a worker change, the need to provide individual monitoring for that worker will

23 be reevaluated.

24

25 (3) Monitoring equipment is identified by type, sensitivity, calibration methods and 

26 frequency, availability, and planned use to protect health and safety. The ranges of 

27 sensitivity for the proposed external radiation monitors are consistent with those 

28 appropriate to the facility operation. All monitoring equipment has a lower limit of 

29 detection that allows measurement of 10 percent of the applicable limits. Planned 

30 surveys of external radiation are consistent with the guidance in Regulatory Guide 8.30, 

31 Revision 1 (NRC, 2002a, Section 1). 

32

33 (4) Plans for documentation of radiation exposures are consistent with the approach in 

34 Regulatory Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation 

35 Dose Data,” Revision 2 (NRC, 2005). 

36

37 The application presents radiation dose levels for corrective action that are consistent 

38 with the regulatory requirements in 10 CFR Part 20. 

39

40 Radiation doses will be kept ALARA in accordance with 10 CFR 20.1101(b) and (d), 

41 10 CFR 20.1702 and 10 CFR 20.1704(a) and consistent with the approach described in

42 Regulatory Guide 8.10, “Operating Philosophy for Maintaining Occupational Radiation 

43 Exposures as Low as Is Reasonably Achievable,” Revision 1 (NRC, 1977) and 

44 Regulatory Guide 8.31, “Information Relevant to Ensuring That Occupational Radiation 

45 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable,” 

46 Revision 1 (NRC, 2002b) or NRC-approved equivalent.

47

48 (5) The applicant monitoring program is adequate to identify sources of beta radiation (skin, 

49 extremity, lens of eye) resulting from the decay products of U-238 when effective 

50 shielding is not present (e.g., maintenance operations) and is consistent with Regulatory 

51 Guide 8.30, Revision 1 (NRC, 2002a).
Radiation Safety Controls and Monitoring

6-3

1 (6) The monitoring program is sufficient to detect gamma radiation from uranium decay 

2 products in areas where large volumes of uranium may be present (e.g., processing 

3 tanks, yellowcake storage areas) and is consistent with Regulatory Guide 8.30, 

4 Revision 1 (NRC, 2002a).

5

6 (7) The program for external exposure monitoring and determining doses from external 

7 exposure is consistent with Regulatory Guide 8.34 (NRC, 1992, Section C).

8

9 6.1.4 Evaluation Findings

10

11 If the staff determines that no license conditions are required for the external radiation exposure 

12 monitoring program because the applicant or licensee provided adequate and complete 

13 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

14 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

15 has completed its review of the external radiation exposure monitoring program at the 

16 conventional uranium mill or heap leach facility in accordance with Section 6.1.3 of the standard 

17 review plan.” Following this sentence, state what information the applicant provided in the 

18 application. As discussed in the introduction of this SRP, a bullet or sentence format may be 

19 used to list what information the applicant has provided. 

20

21 After the description of the information the applicant provided, the following or a similar 

22 statement can be added: “Based on the review conducted by NRC staff, the information 

23 provided in the application meets the applicable acceptance criteria of Section 6.1.3 of the 

24 standard review plan. Therefore, NRC staff concludes that the applicant’s external radiation 

25 exposure monitoring program is acceptable and is in compliance with 10 CFR 20.1101, which 

26 defines a radiation protection program and ALARA requirements; 10 CFR 20.1201, which 

27 defines occupational dose limits; 10 CFR 20.1501, which provides requirements of surveying 

28 and radiation monitoring; 10 CFR 20.1502, which defines conditions requiring individual 

29 monitoring of external dose; and 10 CFR 20.2106, which describes records of individual 

30 monitoring results.” As a concluding statement, indicate the reason why the applicant’s 

31 information is considered adequate and complete, and why or how that information complies 

32 with the identified regulatory requirements.

33

34 If license conditions are needed, then a more detailed discussion is typically required. Begin 

35 this section with the sentence: “NRC staff has completed its review of the external radiation 

36 exposure monitoring program at the conventional uranium mill or heap leach facility in 

37 accordance with Section 6.1.3 of the standard review plan.” Following this sentence, state what 

38 information the applicant provided in the application, including identification of the information 

39 that was omitted or inadequate. As discussed in the introduction of this SRP, a bullet or 

40 sentence format may be used to list what information the applicant has provided. Next, state 

41 why a license condition is needed, followed by the license condition or conditions. 

42

43 In a separate paragraph following the discussion of the required license condition(s), include the 

44 statement: “Based on the review conducted by NRC staff, the information provided in the 

45 application, supplemented by provisions of the license condition(s) discussed above, meets the 

46 applicable acceptance criteria of Section 6.1.3 of the standard review plan. Therefore, NRC 

47 staff concludes that the applicant’s external radiation exposure monitoring program is 

48 acceptable and is in compliance with 10 CFR 20.1101, which defines a radiation protection 

49 program and ALARA requirements; 10 CFR 20.1201, which defines occupational dose limits; 

50 10 CFR 20.1501, which provides requirements of surveying and radiation monitoring;

51 10 CFR 20.1502, which defines conditions requiring individual monitoring of external dose; and 
Radiation Safety Controls and Monitoring

6-4

1 10 CFR 20.2106, which describes records of individual monitoring results.” If not discussed in 

2 the preceding paragraph(s), include a statement or summation as to why or how the application 

3 and license condition(s) jointly comply with the identified regulatory requirements.

4

5 6.1.5 References

6

7 NRC. Regulatory Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation 

8 Dose Data.” Rev. 2. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2005.

9

10 –––––. Regulatory Guide 8.30, “Health Physics Surveys in Uranium Recovery Facilities.” 

11 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002a. 

12

13 –––––. Regulatory Guide 8.31, “Information Relevant to Ensuring That Occupational Radiation 

14 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable.” 

15 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002b.

16

17 –––––. Regulatory Guide 8.34, “Monitoring Criteria and Methods To Calculate Occupational 

18 Radiation Doses.” Washington, DC: NRC, Office of Nuclear Regulatory Research. 1992. 

19

20 –––––. Regulatory Guide 8.10, “Operating Philosophy for Maintaining Occupational Radiation 

21 Exposures as Low as Is Reasonably Achievable.” Rev. 1. Washington, DC: NRC, Office of 

22 Standards Development. 1977. 

23

24 6.2 Airborne Radioactivity Monitoring Program

25

26 6.2.1 Areas of Review 

27

28 The staff should review the workplace airborne radioactivity monitoring program proposed for 

29 assessing concentrations and quantities of radioactive materials released within the restricted 

30 area of the facility. The staff should review the following areas:

31

32 • Technical bases proposed for determining radionuclide concentrations for demonstrating 

33 compliance with standards;

34

35 • Frequency of sampling and analysis;

36

37 • The types and sensitivity of analysis for the counting device;

38

39 • Action levels and corrective action requirements; and

40

41 • Minimum number and criteria for locating monitoring stations.

42

43 In addition to the aforementioned areas, the staff should review the proposed airborne 

44 radioactivity monitoring program to determine concentrations of airborne radioactive materials 

45 (including radon) within the restricted area during routine and nonroutine operations, 

46 maintenance, and cleanup. This review should include criteria for determining airborne 

47 radioactivity monitoring locations and sampling frequency with respect to process operations 

48 and personnel occupancy, as well as analytical procedures and sensitivity and instrument 

49 calibration requirements. Action levels, audits, and corrective action requirements also should 

50 be evaluated.
Radiation Safety Controls and Monitoring

6-5

1 6.2.2 Review Procedures

2

3 Staff should use the following procedures when reviewing the airborne radioactivity

4 monitoring program:

5

6 (1) Verify that the applicant provided sufficient information regarding estimated occupational 

7 doses and that those doses meet ALARA guidelines as described in Regulatory 

8 Guide 8.10, “Operating Philosophy for Maintaining Occupational Radiation Exposures as 

9 Low as Is Reasonably Achievable,” Revision 1 (NRC, 1977). Furthermore, review the 

10 type of verification program the applicant proposes. If calculations are proposed to 

11 demonstrate compliance, ensure that the applicant agrees to perform air monitoring 

12 to confirm the licensing basis and the validity of calculations used for calculating 

13 dose. This information should meet, in part, the requirements of 10 CFR 20.1101 

14 and 10 CFR 20.1501.

15

16 (2) Determine whether the proposed locations of the airborne radioactivity monitoring 

17 stations are consistent with guidance in Regulatory Guide 8.25, “Air Sampling in the 

18 Workplace,” Revision 1 (NRC, 1992) and Regulatory Guide 8.30, “Health Physics 

19 Surveys in Uranium Recovery Facilities,” Revision 1 (NRC, 2002a, Sections 2.1, 2.2, 

20 and 2.3) if an airborne radioactivity monitoring program is proposed. This information 

21 should meet, in part, the requirements of 10 CFR 20.1501.

22

23 (3) Ensure that the applicant correctly determines the derived air concentration (DAC) for 

24 mixtures of radionuclides. This information should meet, in part, the requirements of 

25 10 CFR 20.1204(e), (f), and (g). 

26

27 (4) Confirm that the applicant provides one or more drawings that depict the facility 

28 layout and the location of samplers for airborne radioactivity and provides a basis for the 

29 location of the samplers. This information should meet, in part, the requirements of 

30 10 CFR 20.1501.

31

32 (5) Verify that monitoring equipment is identified by type, sensitivity, calibration methods and 

33 frequency, availability, range of sensitivity, and planned use to accurately measure 

34 concentrations of airborne radioactive species. This information should meet, in part, 

35 the requirements of 10 CFR 20.1501.

36

37 (6) Determine whether planned surveys of airborne radioactivity are consistent with the 

38 guidance in Regulatory Guide 8.30, “Health Physics Surveys in Uranium Recovery 

39 Facilities,” Revision 1 (NRC, 2002a). This information should meet, in part, the 

40 requirements of 10 CFR 20.1101, 10 CFR 20.1501, 10 CFR 20.1701, 10 CFR 20.1702, 

41 and 10 CFR 20.1902(d).

42

43 (7) Confirm that the proposed monitoring program is sufficient to adequately protect workers 

44 from radon gas releases from venting of processing tanks and from yellowcake dust 

45 from drying operations, spills, and maintenance activities and is consistent with 

46 Regulatory Guide 8.25, Revision 1 (NRC, 1992) and Regulatory Guide 8.30, Revision 1

47 (NRC, 2002a, Sections 2.2 and 2.3). This information should meet, in part, the 

48 requirements of 10 CFR 20.1101, 10 CFR 20.1501, 10 CFR 20.1701, 10 CFR 20.1702, 

49 and 10 CFR 20.1902(d).

50
Radiation Safety Controls and Monitoring

6-6

1 (8) Verify that the applicant uses appropriate techniques to measure airborne uranium, 

2 Ra-226, and Th-230. This information should meet, in part, the requirements of 

3 10 CFR 20.1101, 10 CFR 20.1501, 10 CFR 20.1701, 10 CFR 20.1702, and 

4 10 CFR 20.1902(d).

5

6 (9) Verify that plans for documentation of doses from airborne radioactivity exposures are 

7 consistent with the requirements in 10 CFR 20.2102, 10 CFR 20.2103, 10 CFR 20.2106, 

8 10 CFR 20.2110, and the recommendations in Regulatory Guide 8.7, “Instructions for 

9 Recording and Reporting Occupational Radiation Dose Data,” Revision 2 (NRC, 2005). 

10

11 (10) Confirm that the applicant demonstrates that respirators will routinely be used for 

12 operations within drying and packaging areas and identifies the criteria for determining 

13 when respirators will be required for special jobs or emergency situations consistent with 

14 guidance in Regulatory Guide 8.15, “Acceptable Programs for Respiratory Protection,” 

15 Revision 1 (NRC, 1999) and Regulatory Guide 8.31, “Information Relevant to Ensuring 

16 that Occupational Radiation Exposures at Uranium Recovery Facilities Will Be as Low 

17 as Is Reasonably Achievable,” Revision 1 (NRC, 2002b, Section 2.7). This information 

18 should meet, in part, the requirements of 10 CFR 20.1703.

19

20 (11) Verify that the historical airborne radioactivity monitoring program and the airborne 

21 radioactivity monitoring program results are included through the most recent reporting 

22 period preceding application submittal for license renewal applications. This information 

23 should meet, in part, the requirements of 10 CFR 20.1101.

24

25 6.2.3 Acceptance Criteria

26

27 The airborne radioactivity monitoring program within the restricted area is acceptable if it meets 

28 the following criteria: 

29

30 (1) The program:

31

32 • Provides data to analyze maximum worker exposure in accordance with 

33 10 CFR 20.1203 and 10 CFR 20.1204 (e.g., anywhere within the permit 

34 area) and

35

36 • Performs airborne radioactivity monitoring consistent with guidance so that the 

37 applicant can confirm the licensing basis and the validity of calculations used for 

38 calculating dose, if the applicant proposes calculations to demonstrate 

39 compliance with 10 CFR 20.1203 and 10 CFR 20.1204.

40

41 (2) If the applicant proposes airborne monitoring, the proposed locations of the monitoring 

42 stations are presented and are consistent with guidance in Regulatory Guide 8.25, 

43 Revision 1 (NRC, 1992) and Regulatory Guide 8.30, Revision 1 (NRC, 2002a, 

44 Sections 2.1, 2.2, and 2.3). The proposed airborne monitoring program samples radon 

45 and air particulates in accordance with Regulatory Guide 8.25, Revision 1 (NRC, 1992) 

46 and Regulatory Guide 8.30, Revision 1 (NRC, 2002a) and air samples to be analyzed for 

47 Rn-222 will not be composited and will be analyzed quickly enough to minimize decay 

48 losses. The criteria used in selecting sampling locations are provided. 

49

50
Radiation Safety Controls and Monitoring

6-7

1 (3) The applicant calculates the DAC for mixtures of radionuclides in accordance with 

2 the following:

3

4 (a) If the identity of each radionuclide in a mixture is known, the DAC for the mixture 

5 is the sum of the ratios of the concentration to the appropriate DAC value for 

6 each radionuclide in the mixture.

7

8 (b) If the identity of each radionuclide in a mixture is known, but the concentration of 

9 one or more of the radionuclides in the mixture is not known, the DAC for the 

10 mixture is the most restrictive DAC of any radionuclide in the mixture. 

11

12 (c) If the applicant states that natural uranium is the primary radionuclide for all 

13 airborne particulate samples, then the applicant will analyze composite samples 

14 from each of the air particulate monitoring locations and use the results of these 

15 samples to disregard certain radionuclides in the mixture to determine the DAC if:

16

17 (i) The licensee uses the total activity of the mixture to determine 

18 compliance with dose limits in § 20.1201 and monitoring requirements in 

19 § 20.1502(b);

20

21 (ii) The concentration of any disregarded radionuclide is less than 10 percent 

22 of its DAC; and

23

24 (iii) The sum of the percentages of disregarded radionuclides is less than 

25 30 percent.

26

27 (4) The applicant provides one or more drawings that depict the facility layout and the 

28 location of samplers for airborne radioactivity. Locations are based, in part, on a 

29 determination of airflow patterns in areas where monitoring is needed, and the

30 determination of monitoring locations is consistent with Regulatory Guide 8.30, 

31 Revision 1 (NRC, 2002a). 

32

33 (5) Monitoring equipment is identified by type, sensitivity, calibration methods and 

34 frequency, availability, and planned use to accurately measure concentrations of 

35 airborne radioactive species. The application also demonstrates that the ranges of 

36 sensitivity are appropriate for the facility operation. 

37

38 (6) Planned surveys of airborne radioactivity are consistent with the guidance in Regulatory 

39 Guide 8.30, Revision 1 (NRC, 2002a). 

40

41 (7) The proposed monitoring program is sufficient to adequately protect workers from radon 

42 gas releases from venting of processing tanks and from yellowcake dust from drying 

43 operations, spills, and maintenance activities and is consistent with Regulatory 

44 Guide 8.25, Revision 1 (NRC, 1992). The air sampling program is consistent with 

45 Regulatory Guide 8.30, Revision 1 (NRC, 2002a).

46

47 (8) The applicant uses appropriate techniques to measure uranium in air. If Ra-226 and 

48 Th-230 may also be present in the air, additional characterization of the radionuclides in 

49 the sample is provided because gross alpha counting alone will not be able to 

50 differentiate specific radionuclides.

51
Radiation Safety Controls and Monitoring

6-8

1 (9) Plans to document doses from airborne radioactivity exposures are consistent with the 

2 requirements in 10 CFR 20.2102, 10 CFR 20.2103, 10 CFR 20.2106, 10 CFR 20.2110, 

3 and the recommendations in Regulatory Guide 8.7, Revision 2 (NRC, 2005).

4

5 (10) The applicant demonstrates that respirators will routinely be used for operations within 

6 drying and packaging areas and identifies the criteria for determining when respirators 

7 will be required for special jobs or emergency situations. The respiratory protection 

8 program is consistent with guidance in Regulatory Guide 8.15, Revision 1 (NRC, 1999) 

9 and Regulatory Guide 8.31, Revision 1 (NRC, 2002b, Section 2.7).

10

11 (11) For license renewal applications, the historical airborne radioactivity monitoring program 

12 results are included through the most recent reporting period preceding application 

13 submittal. The effectiveness of the historical program is discussed with regard to all 

14 applicable regulatory requirements. Long-term trends are discussed, and any short-term 

15 deviations from the long-term trends are explained.

16

17 6.2.4 Evaluation Findings

18

19 If the staff determines that no license conditions are required for the airborne radioactivity 

20 monitoring program because the applicant or licensee provided adequate and complete 

21 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

22 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

23 has completed its review of the airborne radioactivity monitoring program at the conventional 

24 uranium mill or heap leach facility in accordance with Section 6.2.3 of the standard review plan.” 

25 Following this sentence, state what information the applicant provided in the application. As 

26 discussed in the introduction of this SRP, a bullet or sentence format may be used to list what

27 information the applicant has provided. 

28

29 After the description of the information the applicant provided, the following or a similar 

30 statement can be added: “Based on the review conducted by NRC staff, the information 

31 provided in the application meets the applicable acceptance criteria of Section 6.2.3 of the 

32 standard review plan. Therefore, NRC staff concludes that the applicant’s airborne radioactivity

33 monitoring program is acceptable and is in compliance with 10 CFR 20.1101, which defines the 

34 radioactivity protection program and ALARA requirements; 10 CFR 20.1203, which provides 

35 requirements for determination of external exposure from airborne radioactivity; 10 CFR 

36 20.1204, which provides requirements for determination of internal exposure; 10 CFR 20.1501, 

37 which requires surveys and monitoring; 10 CFR 20.1701, which requires use of process or 

38 engineering controls; 10 CFR 20.1702, which allows employees to limit dose to individuals by 

39 controlling access, limiting exposure times, prescribing use of respiratory equipment, or using

40 other controls; 10 CFR 20.1703, which defines the use of individual respiratory equipment; 

41 10 CFR 20.1902(d), which requires posting of airborne radioactivity areas; 10 CFR 20.2102, 

42 which describes the means of compliance when summing internal and external doses; 

43 10 CFR 20.2103, which requires determination of dose from airborne external radiation; 

44 10 CFR 20.2106, which defines the requirements of records of individual monitoring results;

45 and 10 CFR 20.2110, which further defines records of individual monitoring results.” As a 

46 concluding statement, indicate the reason why the applicant’s information is considered 

47 adequate and complete, and why or how that information complies with the identified 

48 regulatory requirements.

49

50 If license conditions are needed, then a more detailed discussion is typically required. Begin 

51 this section with the sentence: “NRC staff has completed its review of the airborne radioactivity
Radiation Safety Controls and Monitoring

6-9

1 monitoring program at the conventional uranium mill or heap leach facility in accordance with 

2 Section 6.2.3 of the standard review plan.” Following this sentence, state what information the 

3 applicant provided in the application, including identification of the information that was omitted 

4 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

5 used to list what information the applicant has provided. Next, state why a license condition is 

6 needed, followed by the license condition or conditions. 

7

8 In a separate paragraph following the discussion of the required license condition(s), include the 

9 statement: “Based on the review conducted by NRC staff, the information provided in the 

10 application, supplemented by provisions of the license condition(s) discussed above, meets the 

11 applicable acceptance criteria of Section 6.2.3 of the standard review plan. Therefore, NRC 

12 staff concludes that the applicant’s airborne radioactivity monitoring program is acceptable and 

13 is in compliance with 10 CFR 20.1101, which defines the radiation protection program and 

14 ALARA requirements; 10 CFR 20.1203, which provides requirements for determination of 

15 external exposure from airborne radioactivity; 10 CFR 20.1204, which provides requirements for 

16 determination of internal exposure; 10 CFR 20.1501, which requires surveys and monitoring; 

17 10 CFR 20.1701, which requires use of process or engineering controls; 10 CFR 20.1702, 

18 which allows employees to limit dose to individuals by controlling access, limiting exposure 

19 times, prescribing use of respiratory equipment, or using other controls; 10 CFR 20.1703, which 

20 defines the use of individual respiratory equipment; 10 CFR 20.1902(d), which requires posting 

21 of airborne radioactivity areas; 10 CFR 20.2102, which describes the means of compliance 

22 when summing internal and external doses; 10 CFR 20.2103, which requires determination of 

23 dose from airborne external radiation; 10 CFR 20.2106, which defines the requirements of 

24 records of individual monitoring results; 10 CFR 2110, which further defines records of individual 

25 monitoring results.” If not discussed in the preceding paragraph(s), include a statement or 

26 summation as to why or how the application and license condition(s) jointly comply with the 

27 identified regulatory requirements.

28

29 6.2.5 References

30

31 NRC. Regulatory Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation 

32 Dose Data.” Rev. 2. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2005. 

33

34 –––––. Regulatory Guide 8.30, “Health Physics Surveys in Uranium Recovery Facilities.” 

35 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002a. 

36

37 –––––. Regulatory Guide 8.31, “Information Relevant to Ensuring that Occupational Radiation 

38 Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable.” 

39 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002b. 

40

41 –––––. Regulatory Guide 8.15, “Acceptable Programs for Respiratory Protection.” Rev. 1.

42 Washington, DC: NRC, Office of Nuclear Regulatory Research. 1999. 

43

44 –––––. Regulatory Guide 8.25, “Air Sampling in the Workplace.” Rev. 1. Washington, DC: 

45 NRC, Office of Nuclear Regulatory Research. 1992. 

46

47 –––––. Regulatory Guide 8.10, “Operating Philosophy for Maintaining Occupational Radiation 

48 Exposures as Low as Is Reasonably Achievable.” Rev. 1. Washington, DC: NRC, Office of 

49 Standards Development. 1977. 

50
Radiation Safety Controls and Monitoring

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1 6.3 Exposure Calculations

2

3 6.3.1 Areas of Review

4

5 The staff should review the methodologies proposed to calculate the exposures to radioactive 

6 materials by personnel in work areas where airborne radioactive materials could exist. This 

7 review should include methods to determine exposures during routine and nonroutine

8 operations, maintenance, and cleanup activities. 

9

10 6.3.2 Review Procedures

11

12 Staff should use the following procedures when reviewing exposure calculations:

13

14 (1) Verify that the methodologies proposed to determine the intake of radioactive materials 

15 by personnel in work areas where airborne radioactive materials could exist are in 

16 accordance with 10 CFR 20.1204 and 10 CFR 20.1201(a). 

17

18 (2) Ensure that exposure calculations for natural uranium are consistent with Regulatory 

19 Guide 8.30, “Health Physics Surveys in Uranium Recovery Facilities,” Revision 1 (NRC, 

20 2002, Section 3). This information should meet, in part, the requirements of 

21 10 CFR 20.1201(e).

22

23 (3) Ensure that calculations are consistent with Regulatory Guide 8.30, Revision 1 (NRC, 

24 2002) and Regulatory Guide 8.34, “Monitoring Criteria and Methods to Calculate 

25 Occupational Radiation Doses,” (NRC, 1992a, Section C) for airborne radon daughter 

26 exposure (working levels). This information should meet, in part, the requirements of 

27 10 CFR 20.1201(e) and 10 CFR 20.1203.

28

29 (4) Ensure that the DAC from 10 CFR Part 20, Appendix B for the mixture is the most 

30 restrictive DAC of any radionuclide in the mixture if the identity of each radionuclide in 

31 air is known, but the concentration of one or more of the radionuclides in air is not 

32 known. If a mixture exists that does not meet the exclusion rule of 10 CFR 20.1204(g), 

33 ensure that a sum of fractions method will be used to determine the appropriate 

34 DAC. This information should meet, in part, the requirements of 10 CFR 20.1204(f) 

35 and 10 CFR 20.1204(g).

36

37 (5) Ensure that calculations and guidance for prenatal and fetal radiation exposure are 

38 consistent with Regulatory Guide 8.36, “Radiation Dose to the Embryo/Fetus,” (NRC, 

39 1992b) and Regulatory Guide 8.13, “Instruction Concerning Prenatal Radiation 

40 Exposure,” Revision 3 (NRC, 1999). This information should meet, in part, the 

41 requirements of 10 CFR 20.1201(e), 10 CFR 20.1203, 10 CFR 20.1208, 

42 and 10 CFR 20.1502.

43

44 (6) Verify that exposure calculations are presented for routine operations, nonroutine

45 operations, maintenance, and cleanup activities and are consistent with Regulatory 

46 Guide 8.30, Revision 1 (NRC, 2002) and Regulatory Guide 8.34 (NRC, 1992a, 

47 Section C). This information should meet, in part, the requirements of 10 CFR 20.1202 

48 and 10 CFR 20.1206.

49
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1 (7) Ensure that parameters used in exposure calculations are representative of conditions at 

2 the site, and include the time-weighted exposure that incorporates occupancy time and 

3 average airborne concentrations. This information should meet, in part, the 

4 requirements of 10 CFR 20.1202.

5

6 (8) Ensure that estimation of airborne uranium concentrations takes into account the 

7 maximum production capacity requested in the application and the anticipated 

8 efficiencies of airborne particulate control systems reviewed in Sections 3.4 and 6.2 of 

9 this SRP. This information should meet, in part, the requirements of 10 CFR 20.1204 

10 and 10 CFR 20.1201(e).

11

12 (9) Verify that all reporting and record keeping of worker doses conforms with Regulatory 

13 Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation Dose 

14 Data,” Revision 2 (NRC, 2005) and 10 CFR 20.2103.

15

16 (10) Include the historical results of radiation exposure calculations through the most recent 

17 reporting period preceding application submittal in the case of license renewal 

18 applications. This information should meet, in part, the requirements of 10 CFR 20.2104 

19 and 10 CFR 20.2106.

20

21 6.3.3 Acceptance Criteria

22

23 The exposure calculations are acceptable if they meet the following criteria: 

24

25 (1) The methodologies proposed to determine the intake of radioactive materials by 

26 personnel in work areas where airborne radioactive materials could exist are in 

27 accordance with 10 CFR 20.1204 and 10 CFR 20.1201(e). 

28

29 (2) Exposure calculations for natural uranium are consistent with Regulatory Guide 8.30, 

30 Revision 1 (NRC, 2002, Section 3). 

31

32 (3) For airborne radon daughter exposure (working levels), calculations are consistent with 

33 Regulatory Guide 8.30, Revision 1 (NRC, 2002) and Regulatory Guide 8.34 (NRC, 

34 1992a, Section C).

35

36 (4) If the identity of each radionuclide in air is known, but the concentration of one or 

37 more of the radionuclides in air is not known, the DAC from 10 CFR Part 20, 

38 Appendix B, Table 1 for the mixture is the most restrictive DAC of any 

39 radionuclide in the mixture. If a mixture exists that does not meet the exclusion 

40 rule of 10 CFR 20.1204(g), a sum of fractions method will be used to determine 

41 the appropriate DAC. The applicant may need to conduct periodic composite 

42 samples and compare the results to 10 CFR 20.1204(g) to ensure that the 

43 appropriate DAC is used.

44

45 (5) Calculations and guidance for prenatal and fetal radiation exposure are consistent with 

46 Regulatory Guide 8.36 (NRC, 1992b). 

47

48 (6) Exposure calculations are presented for routine operations, nonroutine operations, 

49 maintenance, and cleanup activities and are consistent with Regulatory Guide 8.30, 

50 Revision 1 (NRC, 2002) and Regulatory Guide 8.34 (NRC, 1992a, Section C). 

51
Radiation Safety Controls and Monitoring

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1 (7) Parameters used in exposure calculations are representative of conditions at the site 

2 and include the time-weighted exposure that incorporates occupancy time and average 

3 airborne concentrations.

4

5 (8) Estimation of airborne uranium concentrations takes into account the maximum 

6 production capacity requested in the application and the anticipated efficiencies of 

7 airborne particulate control systems reviewed in Sections 3.5.2 and 6.2 of this SRP. 

8

9 (9) All reporting and record keeping of worker doses is done in conformance with 

10 Regulatory Guide 8.7, Revision 2 (NRC, 2005) and 10 CFR 20.2103. 

11

12 (10) For license renewal applications, the historical results of radiation exposure calculations 

13 are included through the most recent reporting period preceding application submittal.

14

15 6.3.4 Evaluation Findings 

16

17 If the staff determines that no license conditions are required for the exposure calculations 

18 because the applicant or licensee provided adequate and complete information that fully 

19 addresses all relevant regulatory requirements, typically a single paragraph is sufficient for the 

20 evaluation findings section. Begin the section with the sentence: “NRC staff has completed its 

21 review of the exposure calculations at the conventional uranium mill or heap leach facility in 

22 accordance with Section 6.3.3 of the standard review plan.” Following this sentence, state 

23 what information the applicant provided in the application. As discussed in the introduction 

24 of this SRP, a bullet or sentence format may be used to list what information the applicant 

25 has provided. 

26

27 After the description of the information the applicant provided, the following or a similar 

28 statement can be added: “Based on the review conducted by NRC staff, the information 

29 provided in the application meets the applicable acceptance criteria of Section 6.3.3 of the 

30 standard review plan. Therefore, NRC staff concludes that the applicant’s exposure 

31 calculations are acceptable and in compliance with 10 CFR 20.1201(a), which specifies 

32 individual occupational dose limits; 10 CFR 20.1201(e), which defines allowed intake of 

33 soluble uranium; 10 CFR 20.1202, which describes the means of compliance when summing 

34 internal and external doses; 10 CFR 20.1203, for determination of dose from airborne 

35 external radiation; 10 CFR 20.1204, which provides requirements for determination of internal 

36 exposure; 10 CFR 20.1206, which describes the requirements for planned special exposures; 

37 10 CFR 20.1208, which specifies the exposure limits for a fetus; 10 CFR 20.1502, which 

38 defines the conditions requiring individual monitoring; 10 CFR 20.2103, which requires 

39 records of surveys; 10 CFR 20.2104, which requires determination of prior occupational dose; 

40 and 10 CFR 20.2106, which describes requirements for records of individual monitoring 

41 results.” As a concluding statement, indicate the reason why the applicant’s information is 

42 considered adequate and complete, and why or how that information complies with the 

43 identified regulatory requirements.

44

45 If license conditions are needed, then a more detailed discussion is typically required. Begin 

46 this section with the sentence: “NRC staff has completed its review of the exposure calculations 

47 at the conventional uranium mill or heap leach facility in accordance with Section 6.3.3 of the 

48 standard review plan.” Following this sentence, state what information the applicant provided in 

49 the application, including identification of the information that was omitted or inadequate. As 

50 discussed in the introduction of this SRP, a bullet or sentence format may be used to list what
Radiation Safety Controls and Monitoring

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1 information the applicant has provided. Next, state why a license condition is needed, followed 

2 by the license condition or conditions. 

3

4 In a separate paragraph following the discussion of the required license condition(s), include the 

5 statement: “Based on the review conducted by NRC staff, the information provided in the 

6 application, supplemented by provisions of the license condition(s) discussed above, meets the 

7 applicable acceptance criteria of Section 6.3.3 of the standard review plan. Therefore, NRC 

8 staff concludes that the applicant’s exposure calculations are acceptable and in compliance with 

9 10 CFR 20.1201(a), which specifies individual occupational dose limits; 10 CFR 20.1201(e), 

10 which defines allowed intake of soluble uranium; 10 CFR 20.1202, which describes the means 

11 of compliance when summing internal and external doses; 10 CFR 20.1203, for determination of 

12 dose from airborne external radiation; 10 CFR 20.1204, which provides requirements for 

13 determination of internal exposure; 10 CFR 20.1206, which describes the requirements for 

14 planned special exposures; 10 CFR 20.1208, which specifies the exposure limits for a fetus; 

15 10 CFR 20.1502, which defines the conditions requiring individual monitoring; 10 CFR 20.2103, 

16 which requires records of surveys; 10 CFR 20.2104, which requires determination of prior 

17 occupational dose; and 10 CFR 20.2106, which describes requirements for records of individual 

18 monitoring results.” If not discussed in the preceding paragraph(s), include a statement or 

19 summation as to why or how the application and license condition(s) jointly comply with the 

20 identified regulatory requirements.

21

22 6.3.5 References

23

24 NRC. Regulatory Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation 

25 Dose Data.” Rev. 2. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2005. 

26

27 –––––. Regulatory Guide 8.30, “Health Physics Surveys in Uranium Recovery Facilities.” 

28 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002. 

29

30 –––––. Regulatory Guide 8.13, “Instruction Concerning Prenatal Radiation Exposure.” Rev. 3.

31 Washington, DC: NRC, Office of Nuclear Regulatory Research. 1999. 

32

33 –––––. Regulatory Guide 8.34, “Monitoring Criteria and Methods To Calculate Occupational 

34 Radiation Doses.” Washington, DC: NRC, Office of Nuclear Regulatory Research. 1992a. 

35

36 –––––. Regulatory Guide 8.36, “Radiation Dose to the Embryo/Fetus.” Washington, DC: NRC, 

37 Office of Nuclear Regulatory Research. 1992b. 

38

39 6.4 Bioassay Program 

40

41 6.4.1 Areas of Review 

42

43 The staff should review descriptions of the bioassay program and how the bioassay results will 

44 be used to confirm results derived from the airborne radiation monitoring program in Section 6.2

45 of this SRP and the exposure calculations in Section 6.3 of this SRP. The staff should review 

46 the criteria for including workers in the bioassay program, the types and frequencies of 

47 bioassays performed, and action levels applied to the results. 

48

49
Radiation Safety Controls and Monitoring

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1 6.4.2 Review Procedures 

2

3 Staff should use the following procedures when reviewing the bioassay program:

4

5 (1) Verify that the bioassay program is consistent with applicable sections of Regulatory 

6 Guide 8.22, “Bioassay at Uranium Mills,” Revision 1 (NRC, 1988) and Regulatory 

7 Guide 8.31, “Information Relevant to Ensuring that Occupational Radiation Exposures at 

8 Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable,” Revision 1

9 (NRC, 2002) including ALARA requirements. This information should meet, in part, the 

10 requirements of 10 CFR 20.1101 and 10 CFR 20.1204.

11

12 (2) Ensure that the determination of which workers will be monitored in the bioassay 

13 program is consistent with Regulatory Guide 8.22, Revision 1 (NRC, 1988, Section 2). 

14 This information should meet, in part, the requirements of 10 CFR 20.1502 and 

15 10 CFR 20.1703.

16

17 (3) Verify that sampling and analysis frequencies include baseline urinalyses for all new 

18 employees and exit bioassays on termination of employment and are consistent with 

19 Regulatory Guide 8.22, Revision 1 (NRC, 1988, Section 4) and Regulatory Guide 8.9, 

20 “Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program,” 

21 Revision 1 (NRC, 1993). This information should meet, in part, the requirements of 

22 10 CFR 20.1502.

23

24 (4) Ensure that action levels for bioassay monitoring are set in accordance with Regulatory 

25 Guide 8.22, Revision 1 (NRC, 1988, Section 5). This information should meet, in part, 

26 the requirements of 10 CFR 20.1502 and 10 CFR 20.1201(e).

27

28 (5) Ensure that bioassay includes urinalysis for Class D forms of uranium and in-vivo

29 techniques if Classes W or Y forms of uranium are present. This information should 

30 meet, in part, the requirements of 10 CFR 20.1502.

31

32 (6) Ensure that all reporting and record keeping are done in conformance with 

33 the recommendations of Regulatory Guide 8.7, “Instructions for Recording and 

34 Reporting Occupational Radiation Dose Data,” Revision 2 (NRC, 2005) and the 

35 requirements of10 CFR Part 20, Subpart L.

36

37 (7) Ensure that the historical bioassay program results are included through the most 

38 recent reporting period preceding application submittal for license renewal applications. 

39 This information should meet, in part, the requirements of 10 CFR 20.2104 and

40 10 CFR 20.2106.

41

42 6.4.3 Acceptance Criteria

43

44 The bioassay program is acceptable if it meets the following criteria: 

45

46 (1) The bioassay program is consistent with applicable sections of Regulatory Guide 8.22

47 (NRC, 1988) and Regulatory Guide 8.31, Revision 1 (NRC, 2002) including ALARA 

48 requirements. The bioassay program is adequate to confirm results determined from the 

49 airborne radiation monitoring program in Section 6.2 of this SRP and the exposure 

50 calculations in Section 6.3 of this SRP. 

51
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1 (2) The determination of which workers will be monitored in the bioassay program is 

2 consistent with Regulatory Guide 8.22, Revision 1 (NRC, 1988, Section 2). All workers 

3 who are routinely exposed to yellowcake dust are included in the bioassay program. 

4 Primarily, the program will involve workers stationed in yellowcake drying areas and 

5 those who conduct regular maintenance on drying and ventilation/filtration equipment. 

6

7 (3) Sampling and analysis frequencies include baseline urinalyses for all new employees 

8 and exit bioassays on termination of employment and are consistent with Regulatory 

9 Guide 8.22, Revision 1 (NRC, 1988, Section 4) and Regulatory Guide 8.9, Revision 1

10 (NRC, 1993). Sampling and analysis frequencies are sufficient to detect and take 

11 corrective action against high intakes of uranium in the workplace.

12

13 (4) Action levels for bioassay monitoring are set in accordance with Regulatory Guide 8.22, 

14 Revision 1 (NRC, 1988, Section 5) for both radiation dose and chemical toxicity. 

15

16 (5) Bioassay includes urinalysis for Class D forms of the radionuclide and in-vivo techniques 

17 for Classes W and Y forms of the radionuclide.

18

19 (6) All reporting and record keeping are done in conformance with the recommendations of 

20 Regulatory Guide 8.7, Revision 2 (NRC, 2005) and the requirements of 10 CFR Part 20, 

21 Subpart L. 

22

23 (7) For license renewal applications, the historical bioassay program results are included 

24 through the most recent reporting period preceding the application submittal. 

25

26 6.4.4 Evaluation Findings 

27

28 If the staff determines that no license conditions are required for the bioassay program because 

29 the applicant or licensee provided adequate and complete information that fully addresses all 

30 relevant regulatory requirements, typically a single paragraph is sufficient for the evaluation 

31 findings section. Begin the section with the sentence: “NRC staff has completed its review of 

32 the bioassay program at the conventional uranium mill or heap leach facility in accordance with 

33 Section 6.4.3 of the standard review plan.” Following this sentence, state what information the 

34 applicant provided in the application. As discussed in the introduction of this SRP, a bullet or 

35 sentence format may be used to list what information the applicant has provided. 

36

37 After the description of the information the applicant provided, the following or a similar 

38 statement can be added: “Based on the review conducted by NRC staff, the information 

39 provided in the application meets the applicable acceptance criteria of Section 6.4.3 of the 

40 standard review plan. Therefore, NRC staff concludes that the applicant’s bioassay program is 

41 acceptable and is in compliance with 10 CFR 20.1101, which defines the radiation protection 

42 program and ALARA requirements; 10 CFR 20.1201(e), which establishes a limit of intake of 

43 soluble uranium to prevent chemical toxicity; 10 CFR 20.1204, which provides requirements 

44 for the determination of internal exposure; 10 CFR 20.1502, which defines the conditions 

45 requiring individual monitoring; 10 CFR 20.1703, which defines the use of individual 

46 respiratory equipment; 10 CFR 20.2104, which requires determination of prior occupational 

47 dose; 10 CFR 20.2106, which describes requirements for records of individual monitoring 

48 results; and 10 CFR Part 20, Subpart L, which establishes record keeping requirements.” As 

49 a concluding statement, indicate the reason why the applicant’s information is considered 

50 adequate and complete, and why or how that information complies with the identified 

51 regulatory requirements.
Radiation Safety Controls and Monitoring

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1 If license conditions are needed, then a more detailed discussion is typically required. Begin 

2 this section with the sentence: “NRC staff has completed its review of the bioassay program at 

3 the conventional uranium mill or heap leach facility in accordance with Section 6.4.3 of the 

4 standard review plan.” Following this sentence, state what information the applicant provided in 

5 the application, including identification of the information that was omitted or inadequate. As 

6 discussed in the introduction of this SRP, a bullet or sentence format may be used to list what

7 information the applicant has provided. Next, state why a license condition is needed, followed 

8 by the license condition or conditions. 

9

10 In a separate paragraph following the discussion of the required license condition(s), include the 

11 statement: “Based on the review conducted by NRC staff, the information provided in the 

12 application, supplemented by provisions of the license condition(s) discussed above, meets the 

13 applicable acceptance criteria of Section 6.4.3 of the standard review plan. Therefore, NRC 

14 staff concludes that the applicant’s bioassay program is acceptable and is in compliance with 

15 10 CFR 20.1101, which defines the radiation protection program and ALARA requirements; 

16 10 CFR 20.1201(e), which establishes a limit of intake of soluble uranium to prevent chemical 

17 toxicity; 10 CFR 20.1204, which provides requirements for the determination of internal 

18 exposure; 10 CFR 20.1502, which defines the conditions requiring individual monitoring; 

19 10 CFR 20.1703, which defines the use of individual respiratory equipment; 10 CFR 20.2104, 

20 which requires determination of prior occupational dose; 10 CFR 20.2106, which describes 

21 requirements for records of individual monitoring results; and 10 CFR Part 20, Subpart L, which 

22 establishes record keeping requirements.” If not discussed in the preceding paragraph(s),

23 include a statement or summation as to why or how the application and license condition(s) 

24 jointly comply with the identified regulatory requirements.

25

26 6.4.5 References 

27

28 NRC. Regulatory Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation 

29 Dose Data.” Rev. 2. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2005. 

30

31 –––––. Regulatory Guide 8.31, “Information Relevant to Ensuring that Occupational Radiation 

32 Exposures at Uranium Recovery Facilities Will Be as Low as Reasonably Achievable.” Rev. 1.

33 Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002. 

34

35 –––––. Regulatory Guide 8.9, “Acceptable Concepts, Models, Equations, and Assumptions for 

36 a Bioassay Program.” Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory 

37 Research. 1993. 

38

39 –––––. Regulatory Guide 8.22, “Bioassay at Uranium Mills.” Rev. 1. Washington, DC: NRC, 

40 Office of Nuclear Regulatory Research. 1988. 

41

42 6.5 Contamination Control Program 

43

44 6.5.1 Areas of Review

45

46 The staff should review the contamination control program proposed to prevent employees from 

47 entering clean areas or from leaving the site while contaminated with radioactive materials. 

48 Levels of radioactive contamination will be monitored using a radiation survey program. Review 

49 areas include methods for surveying occupational radiation levels, housekeeping, and cleanup 

50 requirements; specifications in process areas to control contamination; frequency of surveys of 
Radiation Safety Controls and Monitoring

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1 clean areas; survey methods; and minimum sensitivity, range, and calibration frequency of 

2 survey equipment. Proposed contamination criteria or action levels for clean areas and for the 

3 release of materials, equipment, and work clothes from clean areas or from the site should be 

4 evaluated. The staff should also review the methods proposed to ensure that the applicant

5 reduces residual contamination below limits before authorizing release of equipment for 

6 unrestricted use. 

7

8 6.5.2 Review Procedures 

9

10 Staff should use the following procedures when reviewing the contamination control program:

11

12 (1) Ensure that radiation surveys of workers will be conducted to prevent contaminated 

13 employees from entering clean areas or from leaving the site consistent with guidance in 

14 Regulatory Guide 8.30, “Health Physics Surveys in Uranium Recovery Facilities,” 

15 Revision 1 (NRC, 2002). This information should meet, in part, the requirements of 10 

16 CFR 20.1501.

17

18 (2) Ensure that requirements for a contamination control program (e.g., maintaining change 

19 areas and personal alpha radiation monitoring before leaving radiation areas) are 

20 included in standard operating procedures or are discussed in the application. This 

21 information should meet, in part, the requirements of 10 CFR 20.1501.

22

23 (3) Verify that action levels for surface contamination are set consistent with Regulatory 

24 Guide 8.30, Revision 1 (NRC, 2002, Section 4). This information should meet, in part, 

25 the requirements of 10 CFR 20.1101.

26

27 (4) Verify that monitoring equipment is described by type, specification of the range, 

28 sensitivity, calibration methods and frequency, availability, and planned use. This 

29 information should meet, in part, the requirements of 10 CFR 20.1501.

30

31 (5) Verify that all reporting and record keeping is done in conformance with the requirements 

32 of 10 CFR Part 20, Subpart L and the recommendations of Regulatory Guide 8.7, 

33 “Instructions for Recording and Reporting Occupational Radiation Dose Data,” Revision 

34 2 (NRC, 2005). 

35

36 (6) Verify that the applicant ensures that radioactivity on equipment or surfaces is not 

37 released for uncontrolled use or covered by paint, plating, or other covering material 

38 unless contamination levels, as determined by a documented survey, are below the 

39 limits specified in Guidance Directive FC 83-23, “Guidelines for Decontamination of 

40 Facilities and Equipment Prior to Release for Unrestricted Use or Termination of 

41 Licenses for Byproduct, Source, or Special Nuclear Material” (NRC, 1993, Appendix G). 

42 This information should meet, in part, the requirements of 10 CFR 20.1501.

43

44 (7) Ensure that volumetrically contaminated material will be evaluated on a case-by-case 

45 basis prior to license termination in accordance with NUREG–1757, Volume 1, 

46 “Consolidated Decommissioning Guidance: Decommissioning Process for Materials 

47 Applicants,” Revision 2 (NRC, 2006, Section 15.11.2) and Guidance Directive FC 83-23 

48 (NRC, 1993, Appendix G).

49

50 (8) Verify that the radioactivity on the interior surfaces of pipes, drain lines, or ductwork will 

51 be determined by making measurements at all traps and other appropriate access 
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1 points, provided that contamination at these locations is likely to be representative of 

2 contamination on the interior of the pipes, drain lines, or ductwork. This information 

3 should meet, in part, the requirements of 10 CFR 20.1501.

4

5 (9) Ensure that the applicant will make a comprehensive radiation survey in conformance 

6 with Regulatory Guide 8.30, Revision 1 (NRC, 2002, Section 2), which establishes 

7 contamination is within the limits specified in Guidance Directive FC 83-23 (NRC, 1993,

8 Appendix G) and is ALARA before equipment or scrap is released for unrestricted use. 

9 This information should meet, in part, the requirements of 10 CFR 20.1501.

10

11 (10) Ensure that appropriate criteria are established to relinquish possession or control of 

12 equipment or scrap having surfaces contaminated with material exceeding the limits 

13 specified in Guidance Directive FC 83-23 (NRC, 1993, Appendix G). This information 

14 should meet, in part, the requirements of 10 CFR 20.1101 and 10 CFR 20.1501.

15

16 6.5.3 Acceptance Criteria 

17

18 The contamination control program is acceptable if it meets the following criteria: 

19

20 (1) Radiation surveys of workers will be conducted to prevent contaminated employees from 

21 entering clean areas or from leaving the site in conformance with guidance in Regulatory 

22 Guide 8.30, Revision 1 (NRC, 2002). The proposed contamination control program will

23 be consistent with the guidance on conducting surveys for contamination of skin and 

24 personal clothing provided in Regulatory Guide 8.30, Revision 1 (NRC, 2002). 

25

26 (2) Requirements for a contamination control program (e.g., maintaining change areas and 

27 personal alpha radiation monitoring before leaving radiation areas) are included in 

28 standard operating procedures or are discussed in the application. These procedures 

29 will be consistent with the guidance on conducting surveys for contamination of skin and 

30 personal clothing provided in Regulatory Guide 8.30, Revision 1 (NRC, 2002). 

31

32 (3) Action levels for surface contamination are set in accordance with Regulatory 

33 Guide 8.30, Revision 1 (NRC, 2002, Section 4). 

34

35 (4) Monitoring equipment is adequately described by type, specification of the range, 

36 sensitivity, calibration methods and frequency, availability, and planned use. The 

37 application demonstrates that the ranges of sensitivity for monitoring equipment will be 

38 appropriate to expected facility operation. 

39

40 (5) All reporting and record keeping is done in conformance with the requirements of 

41 10 CFR Part 20, Subpart L and the recommendations of Regulatory Guide 8.7, Revision 

42 2 (NRC, 2005). 

43

44 (6) The applicant ensures that radioactivity on equipment or surfaces is not released for 

45 uncontrolled use or covered by paint, plating, or other covering material unless 

46 contamination levels, as determined by a documented survey, are below the limits 

47 specified in Guidance Directive FC 83-23 (NRC, 1993, Appendix G) before the covering

48 is applied. A reasonable effort will be made to minimize the contamination before using

49 any covering.

50
Radiation Safety Controls and Monitoring

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1 (7) Existing NRC regulations do not contain generally applicable standards for the 

2 disposition of solid materials with relatively small amounts of radioactivity in, or on, 

3 materials and equipment. Therefore, the applicant commits that the offsite disposition of 

4 volumetrically solid materials prior to license termination is evaluated on a case-by-case 

5 basis in accordance with NUREG–1757, Volume 1, Revision 2 (NRC, 2006, 

6 Section 15.112) and its equivalent, Guidance Directive FC 83-23 (NRC, 1993,

7 Appendix G). NRC staff reviews of applicant requests for the disposition of these 

8 materials using criteria other than those in existing guidance are coordinated with the 

9 NRC Office of Nuclear Material Safety and Safeguards.

10

11 (8) The radioactivity of the interior surfaces of pipes, drain lines, or ductwork will be 

12 determined by making measurements at all traps and other appropriate access points, 

13 provided that contamination at these locations is likely to be representative of 

14 contamination on the interior of the pipes, drain lines, or ductwork. 

15

16 (9) The applicant will make a comprehensive radiation survey in conformance with 

17 Regulatory Guide 8.30, Revision 1 (NRC, 2002, Section 2). Any contamination is within 

18 the limits specified in Guidance Directive FC 83-23 (NRC, 1993, Appendix G) and is 

19 ALARA before release of equipment or scrap for unrestricted use. 

20

21 (10) Appropriate criteria are established to relinquish possession or control of equipment or 

22 scrap having surfaces contaminated with material exceeding the limits specified in 

23 Guidance Directive FC 83-23 (NRC, 1993, Appendix G).

24

25 (a) The applicant will provide detailed information describing the equipment or scrap; 

26 the radioactive contaminants; and the nature, extent, and degree of residual 

27 surface contamination. 

28

29 (b) The applicant will provide a detailed health and safety analysis that reflects the 

30 residual amounts of contaminated materials on surface areas, together with other 

31 considerations such as prospective use of the equipment or scrap, are unlikely to 

32 result in an unreasonable risk to the health and safety of the public. 

33

34 (c) The applicant includes materials created by special circumstances including, but 

35 not limited to, the razing of buildings, transfer of structures or equipment, or 

36 conversion of facilities to a long-term storage facility or to standby status.

37

38 6.5.4 Evaluation Findings 

39

40 If the staff determines that no license conditions are required for the contamination program 

41 because the applicant or licensee provided adequate and complete information that fully 

42 addresses all relevant regulatory requirements, typically a single paragraph is sufficient for the 

43 evaluation findings section. Begin the section with the sentence: “NRC staff has completed its 

44 review of the contamination control program at the conventional uranium mill or heap leach 

45 facility in accordance with Section 6.5.3 of the standard review plan.” Following this sentence, 

46 state what information the applicant provided in the application. As discussed in the introduction 

47 of this SRP, a bullet or sentence format may be used to list what information the applicant 

48 has provided. 

49

50 After the description of the information the applicant provided, the following or a similar 

51 statement can be added: “Based on the review conducted by NRC staff, the information 
Radiation Safety Controls and Monitoring

6-20

1 provided in the application meets the applicable acceptance criteria of Section 6.5.3 of the 

2 standard review plan. Therefore, NRC staff concludes that the applicant’s contamination control 

3 program is acceptable and is in compliance with 10 CFR 20.1101, which defines radiation 

4 protection program and ALARA requirements; 10 CFR 20.1501, which provides survey and 

5 monitoring requirements; and 10 CFR Part 20, Subpart L, which specifies record keeping 

6 requirements.” As a concluding statement, indicate the reason why the applicant’s information 

7 is considered adequate and complete, and why or how that information complies with the 

8 identified regulatory requirements.

9

10 If license conditions are needed, then a more detailed discussion is typically required. Begin 

11 this section with the sentence: “NRC staff has completed its review of the contamination control 

12 program at the conventional uranium mill or heap leach facility in accordance with Section 6.5.3 

13 of the standard review plan.” Following this sentence, state what information the applicant 

14 provided in the application, including identification of the information that was omitted or 

15 inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

16 used to list what information the applicant has provided. Next, state why a license condition is 

17 needed, followed by the license condition or conditions. 

18

19 In a separate paragraph following the discussion of the required license condition(s), include the 

20 statement: “Based on the review conducted by NRC staff, the information provided in the 

21 application, supplemented by provisions of the license condition(s) discussed above, meets the 

22 applicable acceptance criteria of Section 6.5.3 of the standard review plan. Therefore, NRC 

23 staff concludes that the applicant’s contamination control program is acceptable and is in 

24 compliance with 10 CFR 20.1101, which defines radiation protection program and ALARA 

25 requirements; 10 CFR 20.1501, which provides survey and monitoring requirements; and 

26 10 CFR Part 20, Subpart L, which specifies record keeping requirements.” If not discussed in 

27 the preceding paragraph(s), include a statement or summation as to why or how the application 

28 and license condition(s) jointly comply with the identified regulatory requirements.

29

30 6.5.5 References

31

32 NRC. NUREG–1757, Volume 1, “Consolidated Decommissioning Guidance: Decommissioning 

33 Process for Materials Applicants.” Rev. 2. Washington, DC: NRC. September 2006. 

34

35 –––––. Regulatory Guide 8.7, “Instructions for Recording and Reporting Occupational Radiation 

36 Dose Data.” Rev. 2. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2005. 

37

38 –––––. Regulatory Guide 8.30, “Health Physics Surveys in Uranium Recovery Facilities.” 

39 Rev. 1. Washington, DC: NRC, Office of Nuclear Regulatory Research. 2002. 

40

41 –––––. Guidance Directive FC 83-23, “Guidelines for Decontamination of Facilities and 

42 Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, 

43 Source, or Special Nuclear Material.” Washington, DC: NRC, Division of Fuel Cycle Safety and 

44 Safeguards. 1993.
7-1

1 7.0 RECLAMATION AND DECOMMISSIONING PLAN

2

3 This section provides guidance for reviewing the reclamation, decommissioning, and financial 

4 assurance aspects of the proposed facility. Staff should review the proposed plans for 

5 restoration, surface reclamation of surface impoundments, and decommissioning at the 

6 proposed conventional uranium mill or heap leach facility in accordance with NUREG–1620, 

7 “Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings Sites Under Title II 

8 of the Uranium Mill Tailings Radiation Control Act of 1978.” Rev. 1. (NRC, 2003). The reviewer 

9 should consult with NUREG–1620 for details on the areas of reviews, acceptance criteria, 

10 evaluation findings, and underlying regulatory requirements in regard to the reclamation and 

11 decommissioning plan; therefore, such detailed information will not be included in this section. 

12 However, the review, at minimum, should address the following:

13

14 (i) The proposed groundwater constituents of concern, as described in

15 NUREG–1620 (NRC, 2003, Section E 3.2.2), at the point of compliance wells based on 

16 a sound technical and regulatory basis.

17

18 (ii) The proposed decommissioning (radiological cleanup and restoration) of land and 

19 structures (e.g., buildings) in reference to site conditions (e.g., nature and extent of the 

20 contamination, soil background radioactivity), including:

21

22 • Planned decommissioning activities (how and what measurements will be made, 

23 quality assurance/quality control program, gamma guideline levels for soil 

24 cleanup, radioactivity of near surface cover materials (10 CFR Part 40, 

25 Appendix A, Criterion 6(5));

26

27 • A long-term radon flux limit and gamma exposure level for the tailings disposal 

28 cell cover [10 CFR Part 40, Appendix A, Criterion 6(1)];

29

30 • Dust emission limit from tailings that are not covered by standing liquids 

31 (10 CFR Part 40, Appendix A, Criterion 8);

32

33 • Control measures and methods to achieve occupational and public doses that 

34 are as low as is reasonably achievable to protect workers, the public, and the 

35 environment (10 CFR 20.1101); and

36

37 • Verification (final status survey) plan with procedures; and the decommissioning 

38 cost estimate, financial assurance amount, financial assurance updates in 

39 response to facility changes, annual updates, and changes in closure or 

40 decommissioning plans (10 CFR Part 40, Appendix A, Criterion 9).

41

42 The decommissioning plans should also address soil background radioactivity, 

43 cleanup requirements for radioactive contamination (10 CFR Part 40, Appendix A,

44 Criterion 6(1)–6(6)), instruments and procedures, procedures for final radiation surveys 

45 and soil analysis, and disposal of nonradiological hazardous constituents of byproduct 

46 materials (10 CFR Part 40, Appendix A, Criterion 6(7)). Usually, the detailed 

47 conventional uranium mill or heap leach decommissioning plan and the soil cleanup and 

48 verification plan are submitted for NRC approval a year before decommissioning is 

49 scheduled to begin. However, the reclamation plan must describe the expected
Reclamation and Decommissioning Plan

7-2

1 decommissioning activities in enough detail to support the cost estimate needed for 

2 financial assurance purposes.

3

4 (iii) The preliminary decommissioning plan contained in the reclamation plan should include 

5 commitments to provide a detailed plan and cost estimate for NRC approval at least 

6 9 months before decommissioning is expected to begin. The reviewer should determine 

7 whether sufficient detail has been provided in the preliminary decommissioning plan to 

8 justify that the financial assurance amount for decommissioning activities is adequate.

9 Reclamation of the disposal areas, as appropriate, must be completed in a timely 

10 manner after disposal operations cease, in accordance with 10 CFR Part 40, 

11 Appendix A, Criterion 6A(1); however, these actions are not required to be complete as 

12 part of meeting the deadline for final radon barrier construction. The radon barrier needs 

13 to be completed as expeditiously as practical after ceasing operations in accordance 

14 with a written, Commission-approved reclamation plan. The reviewer should document 

15 in the technical evaluation report whether the reclamation plan stipulates if the radon 

16 barrier is to be placed in phases or as a fairly continuous operation. Any milestone 

17 completion dates may be extended if justified by radon release levels, cost 

18 considerations consistent with available technology, in accordance with 10 CFR Part 40, 

19 Appendix A, Criterion 6A(2). As described in NUREG–1620 (NRC, 2003, Section 3.4), 

20 the radon barrier should be effective for 1,000 years, to the extent reasonably 

21 achievable, and in any case for at least 200 years. 

22

23 (iv) Plans for (a) reclaiming slopes, temporary diversion ditches, surface

24 impoundments; (b) reestablishing surface drainage patterns disrupted by the 

25 proposed activities; and (c) restoring the ground surface and structures for 

26 postoperational use (i.e., license termination).

27

28 (v) Methodologies proposed for removal and disposal of contaminated structures and 

29 equipment used during conventional uranium mill or heap leach operations, as well as 

30 techniques for managing hazardous and radioactive waste materials. Staff should 

31 evaluate approaches for (a) identifying radiological hazards before initiating 

32 dismantlement of structures and equipment and (b) detecting and decontaminating

33 removable contamination from such structures and equipment. The staff should review 

34 plans for ensuring that all contaminated facilities and equipment are addressed and are 

35 either to be disposed in a licensed facility, will meet the contamination levels for 

36 unrestricted release, or are designated for reuse at another uranium recovery facility. 

37 The staff should also review provisions made for the removal and disposal of byproduct 

38 material to an existing uranium extraction site or licensed disposal site. 

39

40 (vi) Methodologies for conducting postreclamation and decommissioning 

41 radiological surveys on land and structure surfaces. The staff should review the 

42 radiological verification survey program that will serve as a basis for determining 

43 compliance with NRC concentration limits for license termination (in part, 

44 10 CFR 40.42(g)(4) and (5)). The staff should evaluate the measurement 

45 techniques and sampling procedures proposed.

46

47
Reclamation and Decommissioning Plan

7-3

1 7.1.1 Acceptance Criteria 

2

3 The cost estimate for decommissioning, reclamation, and waste disposal is acceptable if it 

4 meets the following criteria: 

5

6 (1) The financial assurance amount provides sufficient resources to complete facility 

7 reclamation to levels which allow unrestricted use and technical criteria delineated 

8 in10 CFR Part 40, Appendix A, Section I, including decontamination and 

9 decommissioning of buildings and structures, reclamation of surface impoundments, and 

10 soil reclamation by a third party, if necessary. Activities covered by the financial 

11 assurance amount include reclamation, disposal of byproduct material, groundwater and 

12 surface water restoration (if necessary), structure and equipment removal, and closure. 

13 The bases for establishing a financial assurance are satisfied if: 

14

15 (a) All activities included in the cost estimate are activities that are included r in the 

16 reclamation plan. An estimate of the decommissioning/restoration costs is 

17 provided in the application. Once accepted, NRC will review the financial 

18 assurance amount annually to assure that sufficient funds would be available for 

19 completion of the reclamation plan by a third party. 

20

21 (b) The assumptions used for the proposed financial assurance amount are 

22 consistent with what is known about the site [Section 2.0 of the standard review 

23 plan (SRP)} and the design and operations of the facility and its effluent control 

24 system (Sections 3.0, 4.0, and 5.0 of the SRP). To the extent possible, the 

25 applicant should have based these assumptions on experience from generally 

26 accepted industry practices, any research and development at the site, or 

27 previous operating experience in the case of a license renewal. 

28

29 (c) Financial assurance values are based on current dollars (or are adjusted for 

30 inflation) and reasonable costs for the required reclamation activities. Costs are 

31 documented in the application, which includes the basis for the costs. The 

32 applicant commits to funding the approved financial assurance amount 

33 through one of the mechanisms including (i) a surety method or insurance, (ii) 

34 trust funds, an external sinking fund, or prepayment, (iii) irrevocable letters of 

35 credit, or (iv) combinations of these mechanisms or other types of arrangements 

36 as may be approved by the Commission.

37

38 (d) Financial assurance documentation includes a breakdown of costs; the basis for 

39 cost estimates with adjustments for inflation; a minimum 15 percent contingency; 

40 and changes in engineering plans, activities performed, and any other conditions 

41 affecting estimated costs for site closure.

42

43 (2) The applicant has committed to proposed schedules for financial assurance updates in 

44 response to facility changes, annual updates, and changes in closure or 

45 decommissioning plans. The bases for updating the financial assurance are satisfied if:

46

47 (a) The applicant commits to updating the financial assurance value annually, in 

48 response to changes in closure or decommissioning plans, and as necessitated 

49 by changes in the facility and its operations. The annual update will be submitted 

50 90 days prior to the financial assurance anniversary date each year. 

51
Reclamation and Decommissioning Plan

7-4

1 (b) The applicant commits to extending the financial assurance mechanism for an 

2 additional year if NRC has not approved a proposed revision 30 days prior to the 

3 expiration date. 

4

5 (c) The applicant commits to revising the financial assurance arrangement within 

6 3 months of NRC approval of a revised closure (decommissioning) plan if 

7 estimated costs exceed the amount of the existing financial assurance amount. 

8 This revised financial assurance instrument will take effect within 30 days of NRC 

9 written approval of the financial assurance mechanism documents. 

10

11 (d) The applicant commits to submitting for NRC approval an updated financial 

12 assurance estimate to cover any planned expansion or operational change not

13 included in the annual financial assurance update at least 90 days prior to 

14 beginning associated construction. 

15

16 (e) The applicant commits to providing NRC with copies of financial 

17 assurance related correspondence submitted to a state, a copy of the 

18 state’s review, and the final approved financial assurance arrangement. The 

19 applicant also commits that, where the financial assurance is authorized to be 

20 held by the state, the financial assurance covers all appropriate costs.

21

22 (3) Verify that the correct charge for long term surveillance is used and has been properly 

23 adjusted to account for inflation based on the Consumer Price Index published by the 

24 U.S. Department of Labor, Bureau of Labor Statistics.

25

26 7.1.2 Evaluation Findings

27

28 If the staff’s review, as described in this section, results in the acceptance of the financial 

29 assurance cost estimate, the following conclusions may be presented in the technical 

30 evaluation report.

31

32 NRC has completed its review of the financial assurance cost estimate for the 

33 conventional uranium mill or heap leach facility. This review included an evaluation of 

34 the methods that will be used to develop the procedures using the review procedures in 

35 Section 7.1.2 of this SRP and the acceptance criteria outlined in Section 7.1.3 of this 

36 SRP. 

37

38 Based on the information provided in the application and the detailed review conducted 

39 of the financial assurance cost estimate for the conventional uranium mill or heap leach 

40 facility, the staff concludes that the formulas and calculations submitted are accurate. 

41 The NRC staff reviewed the quantities of plant equipment to be removed and disposed 

42 of and found these quantities to be consistent with its knowledge of the site. The NRC 

43 staff determined the licensee had correctly increased the estimate to account for new 

44 infrastructure. For these reasons, the NRC staff determined that adequate justification 

45 for costs related to equipment removal and disposal has been provided. Therefore, 

46 the NRC staff finds that the updated costs are acceptable and are consistent with 

47 10 CFR Part 40, Appendix A, Criterion 9, which requires that each operator establish 

48 financial assurance arrangements. 

49

50
Reclamation and Decommissioning Plan

7-5

1 7.1.3 Reference

2

3 NRC. NUREG–1620, “Standard Review Plan for the Review of a Reclamation Plan for Mill 

4 Tailings Sites Under Title II of the Uranium Mill Tailings Radiation Control Act of 1978.” Rev. 1. 

5 Washington, DC: NRC. June 2003.

6

8-1

1 8.0 ACCIDENTS

2

3 NRC has evaluated the effects of accidents at uranium recovery facilities (NUREG–0706, “Final 

4 Generic Environmental Impact Statement on Uranium Milling, Project M–25” (NRC, 1980)). 

5 Specific areas where NUREG-0706 (NRC, 1980) indicated that consequences could be 

6 significant are (i) radon releases from process streams, (ii) yellowcake dryer explosions, and 

7 (iii) chemical accidents. In addition, the analysis needs to include all chemical forms of uranium 

8 that occur at a conventional uranium mill or heap leach facility.

9

10 The staff review should focus on accident response procedures and personnel training in the 

11 use of these procedures. Radiation safety training is evaluated using Section 4.5 of this 

12 standard review plan (SRP). If an applicant’s operating assumptions, site features, and designs 

13 are not consistent with these analyses in NUREG–0706 (NRC, 1980), the applicant should

14 conduct independent accident analyses. In that case, the staff review should evaluate the 

15 adequacy of these independent analyses. The scope of this review includes radiological, 

16 transportation, and nonradiological accidents. This review should verify that the accident 

17 analyses address a spectrum of accidents ranging in severity from trivial to significant, including 

18 a characterization of the occurrence rate or probability and likely consequences. 

19

20 8.1 Accidents Involving Radioactivity

21

22 8.1.1 Areas of Review

23

24 For all applicants, the staff should examine standard operating and radiological accident 

25 procedures and the training programs for ensuring that personnel can execute them properly. 

26 Conventional uranium mill and heap leach facility radiation safety training programs are 

27 reviewed using Section 4.5 of this SRP. 

28

29 8.1.2 Review Procedures

30

31 Staff should use the following procedures when reviewing accidents involving radioactivity:

32

33 (1) Verify that analyses of radiological accident consequences include mitigation 

34 measures, as appropriate. This information should meet, in part, the requirements of 

35 10 CFR 40.32(c).

36

37 (2) Verify that analyses of radiological accidents include results from operating experience 

38 at similar facilities. For license renewal applications, analyses of radiological accidents 

39 that occurred at the existing facility should be presented, if applicable. This information 

40 should meet, in part, the requirements of 10 CFR 40.32(c).

41

42 (3) Ensure that the applicant’s response program for radiological accidents provides 

43 for notification to NRC in compliance with the requirements of 10 CFR 20.2202 

44 and 10 CFR 20.2203. 

45

46 (4) Verify that the applicant identifies or references adequate procedures to respond to and 

47 mitigate or remediate the likely consequences of radiological accidents. This information 

48 should meet, in part, the requirements of 10 CFR 40.32(c).
Accidents

8-2

1 8.1.3 Acceptance Criteria

2

3 The independent analyses of consequences of accidents involving radioactivity are acceptable if 

4 they meet the following criteria:

5

6 (1) Analyses of radiological accident consequences include mitigation measures, as 

7 appropriate. These scenarios and estimates are supported by properly interpreted data, 

8 calculations, and model results using reasonable assumptions. If consequences cannot 

9 be quantified, an adequate qualitative description of the impacts should be provided. 

10 The applicant has verified that the assumptions in NUREG–0706 (NRC, 1980) are 

11 applicable to the site. 

12

13 (2) Analyses of radiological accidents include results from operating experience at similar 

14 facilities including, for renewal applications, accidents that may have occurred at the 

15 existing facility. Uranium recovery industry experience is used to support any 

16 radiological accident analyses, including consideration of plant design and specific 

17 components that are prone to failure or are known to have failed at other facilities.

18

19 (3) The applicant’s response program for radiological accidents provides for notification to 

20 NRC in compliance with the notification and reporting requirements of 10 CFR 20.2202 

21 and 10 CFR 20.2203. Notification requirements include both immediate and 24-hour 

22 notification, depending on severity. Reporting requirements include both written

23 (including electronic submission, when practicable) and verbal (telephone or emergency 

24 notification system) reports.

25

26 (4) The applicant describes adequate procedures to respond to and mitigate or remediate 

27 the likely consequences of radiological accidents. The applicant describes procedures 

28 related to monitoring, identification, and response to accidents related to (i) radon 

29 release, (ii) yellowcake dryer operations, and (iii) chemical releases as they might affect 

30 radiological accidents.

31

32 8.1.4 Evaluation Findings

33

34 If the staff determines that no license conditions are required for the description of the effects of 

35 radiological accidents because the applicant or licensee provided adequate and complete 

36 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

37 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

38 has completed its review of the description of the effects of radiological accidents at the 

39 conventional uranium mill or heap leach facility in accordance with Section 8.1.3 of the standard 

40 review plan.” Following this statement, state what information the applicant provided in the 

41 application. As discussed in the introduction of this SRP, a bullet or sentence format may be 

42 used to list what information the applicant has provided. 

43

44 After the description of the information the applicant provided, the following or a similar 

45 statement can be added: “Based on the review conducted by NRC staff, the information 

46 provided in the application meets the applicable acceptance criteria of Section 8.1.3 of the 

47 standard review plan. Therefore, NRC staff concludes that the applicant’s description of the 

48 effects of radiological accidents is acceptable and is in compliance with 10 CFR 20.2202 

49 and 10 CFR 20.2203, which define response program requirements for radiological accidents,

50 and 10 CFR 40.32(c), which requires that the applicant’s proposed equipment, facilities, and 

51 procedures be adequate to protect health and minimize danger to life or property.” As a
Accidents

8-3

1 concluding statement, state the reason why the applicant’s information is considered 

2 adequate and complete, and why or how that information complies with the identified 

3 regulatory requirements.

4

5 If license conditions are needed, then a more detailed discussion is typically required. Begin 

6 this section with the sentence: “NRC staff has completed its review of the description of the 

7 effects of radiological accidents at the conventional uranium mill or heap leach facility in 

8 accordance with Section 8.1.3 of the standard review plan.” Following this statement, state 

9 what information the applicant provided in the application, including identification of the 

10 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

11 bullet or sentence format may be used to list what information the applicant has provided. Next, 

12 state why a license condition is needed, followed by the license condition or conditions. 

13

14 In a separate paragraph following the discussion of the required license condition(s), include the 

15 statement: “Based on the review conducted by NRC staff, the information provided in the 

16 application, supplemented by provisions of the license condition(s) discussed above, meets the 

17 applicable acceptance criteria of Section 8.1.3 of the standard review plan. Therefore, NRC 

18 staff concludes that the applicant’s description of the effects of radiological accidents is 

19 acceptable and is in compliance with 10 CFR 20.2202 and 10 CFR 20.2203, which define 

20 response program requirements for radiological accidents, and 10 CFR 40.32(c), which requires 

21 that the applicant’s proposed equipment, facilities, and procedures be adequate to protect 

22 health and minimize danger to life or property.” If not discussed in the preceding paragraph(s),

23 include a statement or summation as to why or how the application and license condition(s) 

24 jointly comply with the identified regulatory requirements.

25

26 8.1.5 Reference

27

28 NRC. NUREG–0706, “Final Generic Environmental Impact Statement on Uranium Milling, 

29 Project M–25.” Washington, DC: NRC. September 1980. 

30

31 8.2 Transportation Accidents

32

33 8.2.1 Areas of Review

34

35 For all applicants, the staff should examine standard operating and transportation accident 

36 procedures and the training programs for ensuring that personnel can execute them properly. 

37 Conventional uranium mill or heap leach facility radiation safety training programs are reviewed 

38 using Section 4.5 of this SRP. 

39

40 8.2.2 Review Procedures 

41

42 Staff should use the following procedures when reviewing transportation accidents:

43

44 (1) Ensure that the applicant has provided analyses of transportation accident 

45 consequences that include mitigation measures, as appropriate. This information should 

46 meet, in part, the requirements of 10 CFR 40.32(c).

47

48 (2) Verify that analyses of transportation accidents include results from operating 

49 experience at similar facilities. This information should meet, in part, the requirements 

50 of 10 CFR 40.32(c).
Accidents

8-4

1 (3) Verify that the applicant identifies or references adequate procedures to respond to and 

2 mitigate or remediate the likely consequences of transportation accidents in the 

3 application. This information should meet, in part, the requirements of 10 CFR 40.32(c).

4

5 8.2.3 Acceptance Criteria

6

7 The independent analyses of consequences of transportation accidents are acceptable if they 

8 meet the following criteria: 

9

10 (1) Analyses of transportation accident consequences include mitigation measures, as 

11 appropriate. For applications that contain independent transportation accident analyses, 

12 these analyses and estimates are supported by properly interpreted data, calculations, 

13 and model results using reasonable assumptions. If consequences cannot be 

14 quantified, an adequate qualitative description of the impacts is provided. Some 

15 operational aspects of transportation activities are addressed through inspections 

16 relevant to the general transportation license requirements.

17

18 (2) Analyses of transportation accidents include results from operating experience at similar 

19 facilities. Uranium recovery industry experience is used to support any transportation 

20 accident analyses, including consideration of plant design and specific components that 

21 are prone to failure or are known to have failed at other facilities. 

22

23 (3) Adequate procedures to respond to and mitigate or remediate the likely consequences 

24 of transportation accidents are identified or referenced in the application. The applicant 

25 has procedures in place to detect and respond to postulated transportation accident 

26 conditions and to mitigate consequences. These procedures include those related to 

27 monitoring, identification, and response to transportation accidents related to accidents 

28 and spills. 

29

30 8.2.4 Evaluation Findings 

31

32 If the staff determines that no license conditions are required for the description of the effects of 

33 transportation accidents because the applicant or licensee provided adequate and complete 

34 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

35 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

36 has completed its review of the description of the effects of transportation accidents at the 

37 conventional uranium mill or heap leach facility in accordance with Section 8.2.3 of the standard 

38 review plan.” Following this statement, state what information the applicant provided in the 

39 application. As discussed in the introduction of this SRP, a bullet or sentence format may be 

40 used to list what information the applicant has provided. 

41

42 After the description of the information the applicant provided, the following or a similar 

43 statement can be added: “Based on the review conducted by NRC staff, the information 

44 provided in the application meets the applicable acceptance criteria of Section 8.2.3 of the 

45 standard review plan. Therefore, NRC staff concludes that the applicant’s description of the 

46 effects of transportation accidents is acceptable and is in compliance with 10 CFR 40.32(c), 

47 which requires that the applicant’s proposed procedures be adequate to protect health and 

48 minimize danger to life or property.” As a concluding statement, state the reason why the 

49 applicant’s information is considered adequate and complete, and why or how that information 

50 complies with the identified regulatory requirements.

51
Accidents

8-5

1 If license conditions are needed, then a more detailed discussion is typically required. Begin 

2 this section with the sentence: “NRC staff has completed its review of the description of the 

3 effects of transportation accidents at the conventional uranium mill or heap leach facility in 

4 accordance with Section 8.2.3 of the standard review plan.” Following this statement, state 

5 what information the applicant provided in the application, including identification of the 

6 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

7 bullet or sentence format may be used to list what information the applicant has provided. Next, 

8 state why a license condition is needed, followed by the license condition or conditions. 

9

10 In a separate paragraph following the discussion of the required license condition(s), include the 

11 statement: “Based on the review conducted by NRC staff, the information provided in the 

12 application, supplemented by provisions of the license condition(s) discussed above, meets the 

13 applicable acceptance criteria of Section 8.2.3 of the standard review plan. Therefore, NRC 

14 staff concludes that the applicant’s description of the effects of transportation accidents is 

15 acceptable and is in compliance with 10 CFR 40.32(c), which requires that the applicant’s 

16 proposed procedures be adequate to protect health and minimize danger to life or property.” 

17 If not discussed in the preceding paragraph(s), include a statement or summation as to 

18 why or how the application and license condition(s) jointly comply with the identified 

19 regulatory requirements.

20

21 8.2.5 References 

22

23 None.

24

25 8.3 Nonradiological Accidents

26

27 8.3.1 Areas of Review

28

29 For all applicants, the staff should examine standard operating and nonradiological accident 

30 procedures and the training programs for ensuring that personnel can execute them properly. 

31

32 8.3.2 Review Procedures 

33

34 Staff should use the following procedures when reviewing nonradiological accidents:

35

36 (1) Verify that analyses of nonradiological accident consequences include mitigation 

37 measures, as appropriate. This information should meet, in part, the requirements 

38 of 10 CFR 40.32(c).

39

40 (2) Verify that analyses of nonradiological accidents include results from operating 

41 experience at similar facilities. This information should meet, in part, the requirements 

42 of 10 CFR 40.32(c).

43

44 (3) Verify that the applicant identifies or references adequate procedures to respond to and 

45 mitigate or remediate the likely consequences of nonradiological accidents. This 

46 information should meet, in part, the requirements of 10 CFR 40.32(c).

47

48
Accidents

8-6

1 8.3.3 Acceptance Criteria

2

3 The independent analyses of consequences of nonradiological accidents are acceptable if they 

4 meet the following criteria: 

5

6 (1) Analyses of nonradiological accident consequences include mitigation measures, as 

7 appropriate. For applications that contain independent accident analyses, these 

8 analyses and estimates are supported by properly interpreted data, calculations, and 

9 model results using reasonable assumptions. If consequences cannot be quantified, an 

10 adequate qualitative description of the impacts is provided. 

11

12 (2) Analyses of nonradiological accidents include results from operating experience at 

13 similar facilities. Uranium recovery industry experience is used to support any other 

14 accident analyses, including consideration of plant design and specific components that 

15 are prone to failure or are known to have failed at other facilities.

16

17 (3) Adequate procedures to respond to and mitigate or remediate the likely consequences 

18 of nonradiological accidents are identified or referenced in the application. The applicant 

19 has procedures in place to address nonradiological accidents. These procedures 

20 include those related to identification of an accident, monitoring, and reporting. 

21

22 8.3.4 Evaluation Findings 

23

24 If the staff determines that no license conditions are required for the description of the effects of 

25 nonradiological accidents because the applicant or licensee provided adequate and complete 

26 information that fully addresses all relevant regulatory requirements, typically a single paragraph 

27 is sufficient for the evaluation findings section. Begin the section with the sentence: “NRC staff 

28 has completed its review of the description of the effects of nonradiological accidents at the 

29 conventional uranium mill or heap leach facility in accordance with Section 8.3.3 of the standard 

30 review plan.” Following this statement, state what information the applicant provided in the 

31 application. As discussed in the introduction of this SRP, a bullet or sentence format may be 

32 used to list what information the applicant has provided. 

33

34 After the description of the information the applicant provided, the following or a similar 

35 statement can be added: “Based on the review conducted by NRC staff, the information 

36 provided in the application meets the applicable acceptance criteria of Section 8.3.3 of the 

37 standard review plan. Therefore, NRC staff concludes that the applicant’s description of the 

38 effects of nonradiological accidents is acceptable and is in compliance with 10 CFR 40.32(c), 

39 which requires that the applicant’s proposed procedures be adequate to protect health and 

40 minimize danger to life or property.” As a concluding statement, state the reason why the 

41 applicant’s information is considered adequate and complete, and why or how that information 

42 complies with the identified regulatory requirements.

43

44 If license conditions are needed, then a more detailed discussion is typically required. Begin 

45 this section with the sentence: “NRC staff has completed its review of the description of the 

46 effects of nonradiological accidents at the conventional uranium mill or heap leach facility in 

47 accordance with Section 8.3.3 of the standard review plan.” Following this statement, state 

48 what information the applicant provided in the application, including identification of the 

49 information that was omitted or inadequate. As discussed in the introduction of this SRP, a 

50 bullet or sentence format may be used to list what information the applicant has provided. Next, 

51 state why a license condition is needed, followed by the license condition or conditions.
Accidents

8-7

1 In a separate paragraph following the discussion of the required license condition(s), include 

2 the statement: “Based on the review conducted by NRC staff, the information provided in 

3 the application, supplemented by provisions of the license condition(s) discussed above, meets 

4 the applicable acceptance criteria of Section 8.3.3 of the standard review plan. Therefore, 

5 NRC staff concludes that the applicant’s description of the effects of nonradiological accidents 

6 is acceptable and is in compliance with 10 CFR 40.32(c), which requires that the applicant’s 

7 proposed procedures be adequate to protect health and minimize danger to life or property.” 

8 If not discussed in the preceding paragraph(s), include a statement or summation as to 

9 why or how the application and license condition(s) jointly comply with the identified 

10 regulatory requirements.

11

12 8.3.5 References

13

14 None.

15

APPENDIX A

GUIDANCE FOR REVIEWING HISTORICAL ASPECTS OF SITE 

PERFORMANCE FOR LICENSE RENEWALS AND AMENDMENTS

A–1

1 GUIDANCE FOR REVIEWING HISTORICAL ASPECTS OF SITE 

2 PERFORMANCE FOR LICENSE RENEWALS AND AMENDMENTS

3

4 For license renewals and amendments, the historical record of site operations, including air and 

5 groundwater quality monitoring, provides valuable information for evaluating the licensing 

6 actions. Following are specific areas where a compliance history or record of site operations 

7 and changes should be provided for review:

8

9  For license renewals, U.S. Nuclear Regulatory Commission (NRC) inspection reports 

10 and license performance reports;

11

12  Amendments and changes to operating practices or procedures;

13

14  License violations identified during NRC or Agreement State site inspections;

15

16  Excursions, incide;nt investigations or root cause analyses, and resultant cleanup 

17 histories or status

18

19  Exceedances of any regulatory standard or license condition pertaining to radiation 

20 exposure, contamination, or release limits;

21

22  Exceedances of any non-radiation contaminant exposure or release limits;

23

24  Updates and changes to any site characterization information important to the evaluation 

25 of exposure pathways and doses including site location and layout; uses of adjacent 

26 lands and waters; population distributions; meteorology; the geologic or hydrologic 

27 setting; ecology; background radiological or nonradiological characteristics; and other 

28 environmental features;

29

30  Environmental effects of site operations including data on radiological and 

31 nonradiological effects and accidents;

32

33 • Updates and changes to factors that may cause reconsideration of alternatives to the 

34 proposed action;

35

36  For license renewals, updates and changes to the economic costs and benefits for the 

37 facility since the last application; and

38

39  For license renewals, the results and effectiveness of any mitigation proposed and 

40 implemented in the original license.

41

42 If, after a review of these historical aspects of site operations, the staff concludes that the site 

43 has been operated so as to protect health and safety and that no unreviewed safety-related 

44 concerns have been identified, then only those changes the license renewal or amendment 

45 application proposes should be reviewed using the appropriate sections of this standard review 

46 plan. Aspects of the facility and its operations that have not changed since the last license 

47 renewal or amendment should not be reexamined.

APPENDIX B

RELATIONSHIP OF 10 CFR PART 40, APPENDIX A, REQUIREMENTS TO 

STANDARD REVIEW PLAN SECTIONS

B–1

1 RELATIONSHIP OF 10 CFR PART 40, APPENDIX A, REQUIREMENTS TO 

2 STANDARD REVIEW PLAN SECTIONS

3

4 This appendix identifies the specific standard review plan sections where the applicable NRC 

5 regulations are addressed. 

6

10 CFR Part 2

Locations in NUREG–2126 Where the 

Regulation Is Addressed

Subpart A. Procedure for issuance, amendment, 

transfer, or renewal of a license, and standard 

design approval

§ 108. Denial of application for failure to supply 

information

Introduction,

Introduction, 

10 CFR Part 20

Locations in NUREG–2126 Where the 

Regulation Is Addressed

Subpart B. Radiation protection programs

§ 1101. Radiation protection programs

Subpart C. Occupational dose limits

§ 1201. Occupational dose limits for adults

(a) License shall control occupational dose to 

individual adults 

(e) Licensee shall limit soluble uranium intake to 

10 mg in a week

§ 1202. Compliance with requirements for 

summation of external and internal doses

§ 1203. Determination of external dose from 

airborne radioactive material

§ 1204. Determination of internal exposure

§ 1206. Planned special exposures

§ 1208. Dose equivalent to an embryo/fetus

Subpart D. Radiation dose limits for individual 

members of the public

§ 1301. Dose limits for individual members of the 

public

2.3, 3.5, 5.3, 6.1, 6.2, 6.4, 6.5

3.5

6.1

6.1, 6.3

6.3, 6.4

6.3

6.2, 6.3

6.2, 6.3, 6.4

6.3

6.3

3.5, 5.3
Appendix B

B–2

§ 1302. Compliance with dose limits for individual 

members of the public

Subpart F..Surveys and monitoring

§ 1501. General

§ 1502. Conditions requiring individual monitoring 

of external and internal occupational dose

Subpart H. Respiratory protection and controls to 

restrict internal exposure in restricted areas

§ 1701. Use of process or other engineering

controls

§ 1702. Use of other controls

§ 1703. Use of individual respiratory protection 

equipment 

Subpart I. Storage and Control of licensed 

material

§ 1801. Security of stored material

§ 1802. Control of material not in storage

Subpart J. Precautionary procedures

§ 1902(d). Posting of airborne radioactivity areas

Subpart K. Waste disposal

§ 2002. Method for obtaining approval of 

proposed disposal procedures

§ 2007. Compliance with environmental and 

health protection regulations

Subpart L.,, Records

§ 2102. Records of radiation protection programs

§ 2103. Records of surveys

§ 2104. Determination of prior occupational dose

2.3, 3.5, 5.3

2.3, 5.3, 6.1, 6.2, 6.5

6.1, 6.3, 6.4

3.5, 5.3, 6.2

6.2

6.2, 6.4

4.6

4.6

6.2

3.5

3.5

6.4, 6.5

6.2

4.2, 6.2, 6.3

6.3, 6.4
Appendix B

B–3

§ 2106. Records of individual monitoring results

§ 2110. Form of records

Subpart M. Reports

§ 2201. Reports of theft or loss

§ 2202. Notification of incidents

§ 2203. Reports of exposures and radiation levels

Appendix B. Annual limits on intake and derived 

air concentrations of radionuclides

6.1, 6.2, 6.3, 6.4

6.2

4.2

4.2, 8.1

8.1

3.5

10 CFR Part 40

Locations in NUREG–2126 Where the 

Regulation Is Addressed

§ 27. General license for custody and long-term 

care of residual radioactive material disposal sites

(b)(2) Detailed description of the final disposal 

site conditions

§ 31. Application for specific licenses

(h) Each application must clearly demonstrate 

how requirements and objectives of Part 40, 

Appendix A have been addressed

§ 32. General requirements for issuance of 

specific licenses

(a) Application is for an authorized purpose

(c) Proposed equipment, facilities, and 

procedures are adequate to protect health and 

minimize danger to life or property

(d) Issuance of license will not be inimical to the 

common defense and security or to the health and 

safety of the public

§ 41. Terms and conditions of licenses

(c) Possession and use of source or byproduct 

material

3.3

Introduction, 1.2, 

Introduction, 2.1, 2.2, 2.3, 2.4, 2.5, 2.7.1, 

2.7.2, 3.1, 3.2, 3.3, 3.5, 5.1

3.1

2.7.2, 3.4, 3.5, 5.1, 5.2, 8.1, 8.2, 8.3

3.4, 5.1

2.7.1, 3.1, 3.2, 3.5, 5.1
Appendix B

B–4

§ 64. Reports

§ 65. Effluent monitoring reporting requirements

4.2

5.3

10 CFR Part 40, Appendix A Criterion

Locations in NUREG–2126 Where the 

Criterion Is Addressed

Criterion 1: Optimize site selection to achieve 

permanent isolation of tailings without 

maintenance.

2.1, 2.5, 2.7.2, 3.3

Criterion 2: Avoid proliferation of small waste 

disposal sites.

3.5

Criterion 3: Dispose of tailings below grade or 

provide equivalent isolation.

2.1, 3.3

Criterion 4: Adhere to siting and design criteria.

(a) Upstream catchment areas must be minimized

(b) Topographic features should provide good 

wind protection

(c) Embankment and cover slopes must be 

relatively flat after final stabilization

(d) A full, self-sustaining vegetative cover must be 

established or a rock cover employed

(e) The impoundment must not be located near a 

capable fault

(f) The impoundment, where feasible, should be 

designed to incorporate features which will 

promote deposition

2.1, 2.7.2

2.1, 2.7.2

3.3

3.3

2.4, 3.3

2.7.2

Criterion 5A: Meet the primary groundwater 

protection standard.

(1) Design, construct, and install an impoundment 

liner that prevents migration of wastes to 

subsurface soil, groundwater, or surface water.

(2) Liner characteristics:

(3) Apply alternate design or operating practices 

that will prevent migration of hazardous 

constituents into groundwater or surface water.

(4) Design, construct, maintain, and operate 

impoundments to prevent overtopping.

3.3

3.3

3.3

3.3
Appendix B

B–5

(5) Design, construct, and maintain dikes to 

prevent massive failure.

Criterion 5B: Conform to the secondary 

groundwater protection standards.

(1) Prevent hazardous constituents from 

exceeding specified concentration limits in the 

uppermost aquifer beyond the point of 

compliance.

(2) Define hazardous constituents as those 

expected to be in or derived from the byproduct 

material, those detected in the uppermost aquifer, 

and those listed in Criterion 13.

(3) Exclude hazardous constituents if they are not 

capable of posing a substantial present or 

potential hazard to human health or the 

environment.

(4) Consider identification of underground 

sources of drinking water and exempted aquifers.

(5) Ensure hazardous constituents at the point of 

compliance do not exceed the background 

concentration, the value in Paragraph 5C, or an 

approved alternate concentration limit.

(6) Establish alternate concentration limits, if 

necessary, after considering practical corrective 

actions, as low as is reasonably achievable 

requirements, and potential hazard to human 

health or the environment.

3.3

5.2

5.2

2.4

2.7.1

5.2

2.7.2

Criterion 5C: Comply with maximum values for 

groundwater protection.

5.2

Criterion 5D: Implement a groundwater corrective 

action program if groundwater protection 

standards are exceeded.

5.2

Criterion 5E: Consider appropriate measures 

when developing and conducting a groundwater 

protection program.

(1) Incorporate leak detection systems for 

synthetic liners, and conduct appropriate testing 

for clay/soil liners.

(2) Use process designs that maximize solution 

recycling and water conservation.

(3) Dewater tailings by process devices or 

3.3, 3.5

3.2

3.3
Appendix B

B–6

properly designed and installed drainage systems.

(4) Neutralize hazardous constituents to promote 

immobilization.

3.5

Criterion 5F: Alleviate seepage impacts where 

they are occurring and restore groundwater 

quality.

5.2

Criterion 5G: Provide appropriate information for 

a disposal system.

(1) Define the chemical and radioactive 

characteristics of waste solutions.

(2) Describe the characteristics of the underlying 

soil and geologic formations.

(3) Define the location, extent, quality, capacity, 

and current uses of groundwater.

3.5

2.5, 2.6, 2.7.1, 3.3

2.7.1

Criterion 5H: Minimize penetration of 

radionuclides into underlying soils when 

stockpiling.

3.1, 3.2

Criterion 6: Install an appropriate cover, and close 

the waste disposal area.

(1) Ensure the cover meets lifetime and 

radioactive material release specifications. This 

establishes a long-term radon flux limit and direct 

gamma exposure (background) level for the 

tailings disposal cell cover. 

(5) Ensure that radon exhalation does not 

significantly exceed background (surrounding 

surface soils) because of the near-surface cover 

material. 

3.3,

3.3,

Criterion 6A: Ensure expeditious completion of 

the final radon barrier.

(3) Authorize disposal of byproduct materials or 

similar materials from other sources if appropriate 

criteria are met.

3.3

Criterion 7: Conduct preoperational and 

operational monitoring programs.

2.3, 2.4, 2.8.1, 2.8.2, 3.5, 5.1, 5.2, 5.4
Appendix B

B–7

Criterion 7A: Establish a detection monitoring 

program to set site-specific groundwater 

protection standards, a compliance monitoring 

system once groundwater protection standards 

have been established, and a corrective action 

monitoring program in conjunction with a 

corrective action program.

3.5

Criterion 8: Conduct milling operations, including 

ore storage, tailings placement, and yellowcake 

drying and packaging operations so that airborne 

releases are as low as is reasonably achievable. 

Dust emissions from tailings that are not covered 

by standing liquids will be minimized using 

methods that include wetting or chemical 

stabilization.

2.3, 3.4, 3.5, 4.2, 4.3, 5.3

Criterion 8A: Conduct and record daily 

inspections of tailings or waste retention systems, 

and report failures or unusual conditions to NRC.

3.3, 4.2, 4.3

Criterion 9: Establish appropriate financial surety 

arrangements for decontamination, 

decommissioning, and reclamation.

7.0

Criterion 10: Establish sufficient funds to cover 

the costs of long-term surveillance and control.

3.5

Criterion 11: Ownership of tailings and their 

disposal sites requirements.

2.7.1

Criterion 12: Minimize or avoid long-term active 

maintenance, and conduct and report on annual 

inspections.

This criterion is not addressed in this 

Standard Review Plan. Please refer to 

NUREG–1620, “Standard Review Plan for 

the Review of a Reclamation Plan for Mill 

Tailings Sites Under Title II of the Uranium 

Mill Tailings Radiation Control Act of 

1978,” Revision 11 for information 

pertaining to this criterion.

Criterion 13: Establish standards for constituents 

reasonably expected to be in or derived from 

byproduct materials and detected in groundwater.

5.2

 1

NRC. NUREG–1620, “Standard Review Plan for the Review of a Reclamation Plan for Mill Tailings Sites Under Title 

II of the Uranium Mill Tailings Radiation Control Act of 1978.” Rev. 1. Washington, DC: U.S. Nuclear Regulatory 

Commission. 2003.

APPENDIX C

GUIDANCE TO THE U.S. NUCLEAR REGULATORY COMMISSION STAFF 

ON THE RADIUM BENCHMARK DOSE APPROACH

C–1

1 GUIDANCE TO THE U.S. NUCLEAR REGULATORY COMMISSION STAFF 

2 ON THE RADIUM BENCHMARK DOSE APPROACH

3

4 C1.0 BACKGROUND

5

6 In 10 CFR 40.4, byproduct material is defined as the tailings or waste produced by the 

7 extraction or concentration of uranium or thorium from any ore processed primarily for its source 

8 material content. Uranium milling is defined as any activity resulting in byproduct material. 

9 Therefore, 10 CFR Part 40, Appendix A applies to both conventional uranium and thorium 

10 recovery facilities. This guidance only addresses uranium recovery facilities because there are 

11 no currently licensed or planned thorium recovery facilities.

12

13 The final rule, “Radiological Criteria for License Termination of Uranium Recovery Facilities,” 

14 (64 FR 17506; April 12, 1999) became effective on June 11, 1999, and added the following 

15 paragraph after the “radium in soil” criteria in 10 CFR Part 40, Appendix A, Criterion 6(6):

16

17 Byproduct material containing concentrations of radionuclides other than radium 

18 in soil, and surface activity on remaining structures, must not result in a total 

19 effective dose equivalent (TEDE) exceeding the dose from cleanup of radium 

20 contaminated soil to the above standard (benchmark dose), and must be at 

21 levels which are as low as is reasonably achievable [ALARA]. If more than one 

residual radionuclide is present in the same 100-square-meter [1,076-ft2 22 ] area, 

23 the sum of the ratios for each radionuclide of concentration present to the 

24 concentration limit will not exceed “1” (unity). A calculation of the potential peak 

25 annual TEDE within 1,000 years to the average member of the critical group that 

26 would result from applying the radium standard (not including radon) on the site 

27 must be submitted for approval. The use of decommissioning plans with 

28 benchmark doses which exceed 100 mrem/yr [1 Sv/yr], before application of 

29 ALARA, requires the approval of the Commission after consideration of the 

30 recommendation of the NRC staff. This requirement for dose criteria does not 

31 apply to sites that have decommissioning plans for soil and structures approved 

32 before June 11, 1999.

33

34 C2.0 RADIUM BENCHMARK DOSE APPROACH

35

36 The general requirements for a decommissioning plan, including verification of soil 

37 contamination cleanup, are addressed in Section 7.4 of the standard review plan (SRP). This 

38 appendix discusses the U.S. Nuclear Regulatory Commission (NRC) staff evaluation of the 

39 radium benchmark dose approach; specifically, dose modeling and its application to site 

40 cleanup activities that should be addressed in the decommissioning plan for those uranium 

41 recovery facilities licensed by NRC and subject to the new requirements for cleanup of 

42 contaminated soil and buildings under 10 CFR Part 40, Appendix A, Criterion 6(6), as amended 

43 in 1999. The facilities that did not have an approved decommissioning plan at the time the rule 

44 became final are required to reduce residual radioactivity (i.e., byproduct material) as defined by 

45 10 CFR Part 40, to levels based on the potential dose, excluding radon, resulting from the 

46 application of the radium (Ra-226) standard at the site. This is referred to as the radium 

47 benchmark dose approach.

48

49 This guidance also applies to any revised decommissioning plan submitted for NRC review and 

50 approval, after the final rule is effective. However, if a subject applicant can demonstrate that 
Appendix C

C–2

1 no contaminated buildings will remain, that Th-230 does not exceed 0.19 Bq/g [5 pCi/g] above 

background in the surface soil and 0.56 Bq/g [15 pCi/g] in subsurface soil in any 100-m2 2

[1,076-ft2 3 ] area that meets the radium standard, and that the natural uranium (i.e., U-nat, U-238, 

4 U-234, and U-235) level is less than 0.19 Bq/g [5 pCi/g] above background, radium benchmark 

5 dose modeling is not required. If future modeling with site-specific parameters for uranium 

6 recovery sites indicates that this is not a protective approach, the guidance will be revised. 

7 Therefore, it would be prudent for a uranium recovery applicant to consider the potential dose 

8 from any residual thorium and uranium.

9

10 The unity “rule” mentioned in Criterion 6(6) applies to all licensed residual radionuclides. 

11 Therefore, if the ore (processed by the facility), tailings, or process fluid analyses indicate that 

12 elevated levels of Th-232 could exist in certain areas after cleanup for Ra-226, some verification 

13 samples in those areas should be analyzed for Th-232 or Ra-228. The thorium (Th-232) chain 

14 radionuclides (above local background levels) in milling waste would have soil cleanup criteria 

15 similar to the uranium chain radionuclides. The staff considers the U.S. Environmental 

16 Protection Agency memorandum of February 12, 1998 (Directive No. 9200.4–25), concerning 

17 use of 40 CFR Part 192 soil criteria for Comprehensive Environmental Response, 

18 Compensation and Liability Act sites, an acceptable approach. This means that the Th-230 

19 and Th-232 should be limited to the same concentration as their radium progeny with the 

20 0.19 Bq/g [5 pCi/g] criterion applying to the sum of the radium (Ra-226 plus Ra-228) as well as 

21 the sum of the thorium (Th-230 plus Th-232) above background.

22

23 C2.1 Radium Benchmark Dose Modeling

24

25 C2.1.1 Areas of Review 

26

27 The radium benchmark dose approach involves calculation of the peak potential dose for the 

28 site resulting from the 0.19 Bq/g [5 pCi/g] concentration of radium in the surface 15 cm [6 in] of 

29 soil. The dose from the 0.56 Bq/g [15 pCi/g] subsurface radium would also be calculated for 

30 any area where the criterion is applied. The dose modeling review involves examining the 

31 computer code or other calculations employed for the dose estimates, the code or calculation 

32 input values and assumptions, and the modeling results (data presentation).

33

34 Evaluation of the radium benchmark dose modeling as proposed in the decommissioning plan

35 requires an understanding of the site conditions and site operations. The relevant site 

36 information presented in the plan or portions of previously submitted documents 

37 (e.g., environmental reports, license renewal applications, reclamation plan, and 

38 characterization survey report) should be reviewed.

39

40 C2.1.2 Review Procedures

41

42 The radium benchmark dose modeling review consists of ascertaining, in accordance with 

43 10 CFR Part 40, Appendix A, Criterion 6(6), that:

44

45 (1) An acceptable dose modeling computer code or other type of calculation has been used;

46

47 (2) Input parameter values appropriate for the site (reasonable considering long-term 

48 conditions and representative of the application) have been used in the modeling;

49
Appendix C

C–3

1 (3) A realistic dose estimate is provided (overly conservative is not acceptable as it would 

2 result in higher allowable levels of uranium or thorium that would not be ALARA); and

3

4 (4) The data presentation is clear and complete.

5

6 C2.1.3 Acceptance Criteria

7

8 The radium benchmark dose modeling results will be acceptable if the dose assessment 

9 (modeling) meets the following criteria:

10

11 (1) Dose Modeling Codes and Calculations

12

13 The assumptions are considered reasonable for the site analysis, and the calculations 

14 employed are adequate. Reference to documentation concerning the code or 

15 calculations is provided [e.g., the RESRAD Handbook and Manual (Argonne National 

16 Laboratory, 1993a, b)].

17

18 The RESRAD code the U.S. Department of Energy (Yu, et al., 2001) developed may be 

19 acceptable for dose calculations because, although the RESRAD groundwater 

20 calculations have limitations, this does not affect the uranium recovery sites that have 

21 deep aquifers (groundwater exposure pathway is insignificant). The DandD code

22 (Kennedy and Strenge, 2001) NRC developed (the code is available at the website 

23 http://www.orau.gov/ddsc/dose/compcode.htm) provides conservative default values, 

24 but does not allow for modeling subsurface soil contamination and does not allow 

25 calculation of source removal due to soil erosion. Both the RESRAD and DandD codes

26 would not be adequate to model the dose from offsite contamination, but codes such as 

27 GENII are acceptable. See NUREG–1727 (NRC, 2000, Appendix C) for 

28 additional information.

29

30 If the code or calculation assumptions are not compatible with site conditions, 

31 adjustments have been made in the input to adequately reflect site conditions. For 

32 example, the RESRAD code assumes a circular contaminated zone. The shape factor 

33 (external gamma, code screen R017) must be adjusted for an area that is not circular.

34

35 The code and/or calculation provide an estimated annual dose as total effective dose 

36 equivalent in mrem/yr. The DandD code provides the annual dose, but RESRAD 

37 calculates the highest instantaneous dose. However, RESRAD results are acceptable 

38 for long-lived radionuclides that do not move rapidly out of surface soils.

39

40 (2) Input Parameter Values

41

42 The code/calculation input data are appropriate for the site and represent current or 

43 long-term conditions, whichever is more applicable to the time of maximum dose. When 

44 code default values are used, they are justified as appropriate (representative) for the 

45 site. Excessive conservatism (i.e., upper bound value) is not used, as this would result 

46 in a higher dose and thus higher levels of uranium and thorium could be allowed to 

47 remain onsite.

48

49 Previously approved MILDOS code input parameter values may not be appropriate, 

50 because derived operational doses in the restricted area may be an order of magnitude 

51 higher than acceptable doses for areas to be released for unrestricted use.
Appendix C

C–4

1

2 Site-specific input values are demonstrated to be average values of an adequate sample 

3 size. Confidence limits are provided for important parameters so that the level of 

4 uncertainty can be estimated for that input value. Alteration of input values considers 

5 that some values are interrelated and relevant parameters are modified accordingly. 

6 The preponderance of important parameter values are based on site measurements and 

7 not on conservative estimates. One or more models consider the annual average range 

8 of parameter values likely to occur within the next 200 years for important parameters 

9 that can reasonably be estimated. Some other considerations for the input parameter 

10 values follow:

11

12 (a) Scenarios for the Critical Group and Exposure Pathways

13

14 The scenario(s) chosen to model the potential dose to the average member of 

the critical group1 15 from residual radionuclides at the site reflect reasonable 

16 probable future land use. The applicant has considered ranching, mining, 

17 home-based business, light industry, and residential farmer scenarios and has 

18 justified the scenarios modeled.

19

20 On the basis of one or more of these projected (within 200 years is reasonably 

21 foreseeable) land uses to define the critical group(s), the applicant has 

22 determined and justified what exposure pathways are probable for potential 

23 exposure of the critical group to residual radionuclides at the site. Dairies are not 

24 likely to be established in the area of former uranium recovery facilities, because 

25 the climate and soil restrict feed production. Even if some dairy cows were to 

26 graze in contaminated areas, the milk would probably be sent for processing 

27 (thus diluted) and not be consumed directly at the site. Therefore, milk 

28 consumption is not a likely ingestion exposure pathway. Also, a pond in the 

29 contaminated area providing a significant quantity of fish for the resident’s diet is 

30 not likely, so the aquatic exposure pathway may not have to be modeled. 

31 However, the external gamma, plant ingestion, and inhalation pathways are likely 

32 to be important.

33

34 The radon pathway is excluded from the benchmark dose calculation as defined 

35 in 10 CFR Part 40, Appendix A, Criterion 6(6). This also reflects the approach in 

36 10 CFR Part 20, Subpart E, “Standards for Protection Against Radiation—

37 Radiological Criteria for License Termination.”

38

39 (b) Source Term

40

41 If the RESRAD code is used, the input includes Pb-210 at the same input value 

42 as for Ra-226. The other radium progeny are automatically included in the code 

43 calculations. The chemical form of the contamination in the environment is 

44 considered in determining input values related to transport or inhalation class 

45 (retention in the lung) for dose conversion factors.

46

 1

As defined in 10 CFR Part 20, “the group of individuals reasonably expected to receive the greatest exposure to 

residual radioactivity for any applicable set of circumstances.”
Appendix C

C–5

1 (c) Time Periods

2

3 The time periods for calculation of the dose from soil Ra-226 include the 

4 1,000-year time frame. The calculated maximum annual dose and the year of 

5 occurrence are presented in the results.

6

7 (d) Cover and Contaminated Zone

8

9 A cover depth of zero is used in the surface contamination model, and a depth of 

10 at least 15 cm [6 in] is used for the subsurface model. The values for area and 

11 depth of contamination are derived from site characterization data. The erosion 

12 rate value for the contaminated zone is less than the RESRAD default value 

13 because in regions drier than normal, the erosion rate is less, as discussed in the 

14 RESRAD Data Collection Handbook (Argonne National Laboratory, 1993a), and 

15 the proposed value is justified. The soil properties are based on site data (sandy 

16 loam or sandy silty loam are typical for uranium recovery sites), and other input 

17 parameters are based on this demonstration of site soil type [see RESRAD 

18 handbook (Argonne National Laboratory, 1993a, pp. 23, 29, 77, and 105)].

19

20 The evapotranspiration coefficient for the semiarid uranium recovery sites is 

21 between 0.6 and 0.99. The precipitation value is based on annual values 

22 averaged over at least 20 years, obtained from the site or from a nearby 

23 meteorological station.

24

25 The irrigation rate value may be zero, or less than a code’s default value, if 

26 supported by data on county or regional irrigation practices (e.g., zero is 

27 acceptable if irrigation water is obtained from a river, not a well). The runoff 

28 coefficient value is based on the site’s soil type, expected land use, and 

29 regional morphology.

30

31 (e) Saturated Zone

32

33 The dry bulk density, porosity, “b” parameter, and hydraulic conductivity values 

34 are based on local soil properties. The hydraulic gradient for an unconfined 

35 aquifer is approximately the slope of the water table. For a confined aquifer, it 

36 represents the difference in potentiometric surfaces over a unit distance.

37

38 If the RESRAD code is used, the nondispersion model parameter is chosen for 

areas greater than 1,000 m2 [10,764 ft2 39 ] (code screen R014), and the well pump 

40 rate is based on irrigation, stock, or drinking water well pump rates in the area.

41

42 (f) Uncontaminated and Unsaturated Strata

43

44 The thickness value represents the typical distance from the soil contamination to 

45 the saturated zone. Because the upper aquifer at uranium recovery sites is often 

46 of poor quality and quantity, the depth of the shallowest well used for irrigation or 

47 stock water in the region is chosen for the unsaturated zone thickness. A value of 

48 18 m [60 ft] is typical for most sites {15 m [50 ft] for the Nebraska site}, but 

49 regional data are provided for justification. The density, porosity, and “b” 

50 parameter values are similar to those for the saturated zone, or any changes 
Appendix C

C–6

1 are justified.

2

3 (g) Distribution Coefficients and Leach Rates

4

5 The distribution coefficient (Kd) is based on the physical and chemical 

6 characteristics of the soil at the site. The leach rate value of zero in the RESRAD 

7 code is acceptable as it allows calculation of the value. If a value greater than 

8 zero is given, the value is justified.

9

10 (h) Inhalation

11

An average inhalation rate value of approximately 8,395 m3

/yr [10,980 ft3 12 /yr] is

13 used for the activity assumed for the rancher or farmer scenario. The mass 

14 loading for inhalation (air dust loading factor) value is justified based on the 

15 average level of airborne dust in the local region for similar activities as assumed 

16 in the model.

17

18 (i) External Gamma

19

20 The shielding factor for gamma is in the range of 0.4 to 0.8 (60 to 20 percent 

21 shielding) based on DandD Parameter data (the DandD code screening default 

22 value is 0.55). The factor is influenced by the type (foundation, materials) of 

23 structures likely to be built on the site and the gamma energy of the radionuclides 

24 under consideration.

25

26 The time fractions for indoor and outdoor occupancy are similar to default values 

27 in RESRAD. For example, the staff would consider fraction values approximating 

28 0.7 indoors and 0.15 outdoors for a resident working at home, and 0.5 outdoors 

29 and 0.25 indoors for the farmer scenario (the remaining fraction allocated to time 

30 spent offsite).

31

32 The site-specific windspeed value is based on adequate site data. The average 

33 annual windspeed for the uranium recovery sites varies from 3.1 to 5.5 m/s 

34 [7 to 13 mph]. The maximum and annual average windspeed are also considered 

35 when evaluating proposed erosion rates.

36

37 (j) Ingestion

38

39 Average consumption values (g/yr) for the various types of foods are based on 

40 average values and are justified. Livestock ingestion parameters are default 

41 values or are otherwise justified.

42

43 For sites with more than 40.5 ha [100 ac] of contamination, the fraction of diet 

44 from the contaminated area is assumed to be 0.25 for the farmer scenario or is 

45 otherwise justified based on current or anticipated regional consumption 

46 practices for home-grown food. When low levels of precipitation exist in the 

47 areas in which uranium recovery facilities are located, extensive gardens or 

48 areas of dense animal grazing are not likely, so the percentage of the diet 

49 obtained from contaminated areas would be lower than the code default value.

50
Appendix C

C–7

1 Note that often the default plant mass loading factor in the DandD code can 

2 reasonably be reduced to 1 percent. The depth of roots is an important input 

3 parameter for uranium recovery applicants using the RESRAD code. The value 

4 is justified based on the type of crops likely to be grown on the site in the 

5 future. For vegetable gardens, a value of 0.3 is more appropriate than the 

6 RESRAD default value of 0.9 m [3 ft] that is reasonable for alfalfa or for a similar 

7 deep-rooted plant.

8

9 (3) Presentation of Modeling Results

10

11 The radium benchmark dose modeling section of the decommissioning plan includes the 

12 code or calculation results as the maximum annual dose (TEDE) in mrem/yr, the year 

13 that this dose would occur, and the major exposure pathways by percentage of total 

14 dose. The modeling section also discusses the likelihood of the various land-use 

15 scenarios modeled (reflecting the probable critical groups) and provides the variations in 

16 dose (dose distribution) created by changing key parameter values to reflect the range of 

17 dose values that are likely to occur on the site. The section also contains the results of a 

18 sensitivity analysis (RESRAD can provide a sensitivity analysis via the graphics function) 

19 to identify the important parameters for each scenario.

20

21 C2.1.4 Evaluation Findings

22

23 If the staff’s review, as described in this section, results in the acceptance of the radium 

24 benchmark dose modeling, the following conclusions may be presented in the safety

25 evaluation report.

26

27 If the staff determines that no license conditions are required for the site benchmark dose 

28 modeling because the applicant or licensee provided adequate and complete information that 

29 fully addresses all relevant regulatory requirements, typically a single paragraph is sufficient for 

30 the evaluation findings section. Begin the section with the sentence: “NRC staff has completed 

31 its review of the site benchmark dose modeling at the conventional uranium mill or heap leach 

32 facility in accordance with Section E2.1.3 of the standard review plan.” Following this sentence, 

33 state what information the applicant provided in the application. As discussed in the introduction 

34 of this standard review plan (SRP), a bullet list or sentence format may be used to list what 

35 information the applicant has provided. 

36

37 After the description of the information the applicant provided, the following or a similar 

38 statement can be added: “Based on the review conducted by NRC staff, the information 

39 provided in the application meets the applicable acceptance criteria of Section E2.1.3 of the 

40 standard review plan. Therefore, NRC staff concludes that the applicant’s site benchmark dose 

41 modeling is acceptable and is in compliance 10 CFR Part 40, Appendix A, Criterion 6(6), which 

42 describes requirements for site benchmark dose modeling.” As a concluding statement, 

43 indicate the reason why the applicant’s information is considered adequate and complete, and 

44 why or how that information complies with the identified regulatory requirements. 

45

46 If license conditions are needed, then a more detailed discussion is typically required. Begin 

47 this section with the sentence: “NRC staff has completed its review of the site benchmark 

48 dose modeling at the conventional uranium mill or heap leach facility in accordance with

49 Section E2.1.3 of the standard review plan.” Following this sentence, state what information the 

50 applicant provided in the application, including identification of the information that was omitted 

51 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 
Appendix C

C–8

1 used to list what information the applicant has provided. Next, state why a license condition is 

2 needed, followed by the license condition or conditions. 

3

4 In a separate paragraph following the discussion of the required license condition(s), include the 

5 statement: “Based on the review conducted by NRC staff, the information provided in the 

6 application, supplemented by provisions of the license condition(s) discussed above, meets the 

7 applicable acceptance criteria of Section E2.1.3 of the standard review plan. Therefore, NRC

8 staff concludes that the applicant’s site benchmark dose modeling is acceptable and is in 

9 compliance with 10 CFR Part 40, Appendix A, Criterion 6(6), which describes requirements for 

10 site benchmark dose modeling.” If not discussed in the preceding paragraph, include a 

11 statement or summation as to why or how the application and license condition(s) jointly comply 

12 with the identified regulatory requirements.

13

14 C2.2 Implementation of the Benchmark Dose

15

16 C2.2.1 Areas of Review

17

18 The results of the radium benchmark dose calculations are used to establish a surface and 

19 subsurface soil dose limit for residual radionuclides other than radium, as well as a limit for 

20 surface activity on structures that will remain after decommissioning. The staff should review 

21 the applicant’s conversion of the benchmark dose limit to soil concentration pCi/g or surface 

activity levels dpm/100 cm2 22 as a first step to determine cleanup levels. Alternatively, the 

23 applicant can derive the estimated dose from the uranium or thorium contamination (as 

24 discussed in Section E2.1.3) and compare this to the radium benchmark dose.

25

26 The staff should also evaluate the proposed cleanup guideline levels (derived concentration 

27 limit) in relation to the ALARA requirement and the unity rule.

28

29 C2.2.2 Review Procedures

30

31 The decommissioning plan section on cleanup criteria should be evaluated for appropriate 

32 conversion of the radium standard benchmark dose to cleanup limits for soil uranium and 

33 thorium and/or surface activity. The plan should also be examined to ensure reasonable 

34 application of ALARA to the cleanup guideline values and application of the unity rule 

35 where appropriate.

36

37 C2.2.3 Acceptance Criteria

38

39 (1) The soil concentration limit is derived from the site radium dose estimate. The modeling 

40 performed to estimate mrem/yr per Bq/g [pCi/g] of Th-230 and/or U-nat follows the 

41 criteria listed in Section E2.1.3. In addition, the U-nat source term input is represented 

42 as percentage of activity by 48.9 percent U-238, 48.9 percent U-234, and 2.2 percent 

43 U-235, or is based on analyses of the ore processed. For a soil uranium criterion 

44 (derived concentration limit), the chemical toxicity is considered in deriving a soil 

45 concentration limit if soluble forms of uranium are present.

46

47 (2) Detailed justification for the inhalation pathway parameters is provided, such as the 

48 determination of the chemical form in the environment, to support the inhalation class.

49
Appendix C

C–9

(3) The derived Th-230 soil limit will not cause any 100 m2 [1.076 ft2 1 ] area to exceed the 

2 Ra-226 limit at 1,000 years (i.e., current concentrations of Th-230 are less than 

3 0.52 Bq/g [14 pCi/g] surface and 1.6 Bq/g [43 pCi/g] subsurface, if Ra-226 is at 

4 approximately background levels).

5

6 (4) In conjunction with the activity limit, the ALARA principle is considered in setting cleanup 

7 levels (derived concentration guideline levels). The ALARA guidance in NUREG–1727 

8 (NRC, 2000, Appendix D) is considered. The proposed levels allow the applicant to 

9 demonstrate that the requirements of 10 CFR 40.42(k) (the premises are suitable for 

10 release, and reasonable effort has been made to eliminate residual radioactive 

11 contamination) can be met.

12

13 (5) In recent practice at mill sites, the ALARA principle is implemented by removing about 

14 5 cm [2 in] more soil than is estimated to achieve the radium standard (reduce any 

15 possible excess or borderline contamination). At recovery facilities, it is generally 

16 cheaper to remove more soil than to do sampling and testing that may indicate failure 

17 and require additional soil removal with additional testing.

18

19 (6) The unity rule is applied to the cleanup if more than one residual radionuclide is present 

in a soil verification grid 100 m2 [1,076 ft2 20 ]. This means that the sum of the ratios for 

21 each radionuclide of the concentration present/concentration limit may not exceed 1 

22 (i.e., unity).

23

24 (7) The subsurface soil standard, if it is to be used, is applied to small areas of deep 

25 excavation where at least 15 cm [6 in] of compacted clean fill is to be placed on the 

26 surface and where that depth of cover is expected to remain in place for the foreseeable 

27 future. The long-term cover depth used in the model is justified.

28

29 (8) The surface activity limit for remaining structures is appropriately derived using an 

30 approved code or calculation. Because recent conservative dose modeling by NRC staff 

has indicated that more than 2,000 dpm/100 cm2 31 alpha (U-nat or uranium chain 

32 radionuclides) in habitable buildings [2,000 hr/yr] could exceed an effective dose 

33 equivalent of 0.25 m Sv/yr [25 mrem/yr], the applicant proposes a total (fixed plus 

34 removable) average surface activity limit for such buildings that is lower than 

2,000 dpm/100 cm2 35 or a higher value is suitably justified.

36

37 (9) If the DandD code is used, data are provided to support that 10 percent or less of the 

38 activity is removable; otherwise, the resuspension factor is scaled to reflect the 

39 site-specific removable fraction. Note that this code assumes that the contamination is 

40 only on the floor, which can be overly conservative. If the RESRAD-Build code is used, 

41 the modeled distribution of contamination on walls and floor is justified.

42

43
Appendix C

C–10

1 C2.2.4 Evaluation Findings

2

3 If the staff’s review, as described in this section, results in the acceptance of the application of 

4 the radium benchmark dose modeling to the site cleanup criteria, the following conclusions may 

5 be presented in the safety evaluation report.

6

7 If the staff determines that no license conditions are required for the site benchmark dose 

8 implementation because the applicant or licensee provided adequate and complete information 

9 that fully addresses all relevant regulatory requirements, typically a single paragraph is sufficient 

10 for the evaluation findings section. Begin the section with the sentence: “NRC staff has 

11 completed its review of the site benchmark dose implementation at the conventional uranium 

12 mill or heap leach facility in accordance with Section E3.1.3 of the standard review plan.” 

13 Following this sentence, state what information the applicant provided in the application. As 

14 discussed in the introduction of this SRP, a bullet list or sentence format may be used to list 

15 what information the applicant has provided. 

16

17 After the description of the information the applicant provided, the following or a similar 

18 statement can be added: “Based on the review conducted by NRC staff, the information 

19 provided in the application meets the applicable acceptance criteria of Section E3.1.3 of the 

20 standard review plan. Therefore, NRC staff concludes that the applicant’s site benchmark dose 

21 implementation is acceptable and is in compliance 10 CFR Part 40, Appendix A, Criterion 6(6), 

22 which describes requirements for site benchmark dose implementation.” As a concluding 

23 statement, indicate the reason why the applicant’s information is considered adequate and 

24 complete, and why or how that information complies with the identified regulatory requirements. 

25

26 If license conditions are needed, then a more detailed discussion is typically required. Begin 

27 this section with the sentence: “NRC staff has completed its review of the site benchmark dose 

28 implementation at the conventional uranium mill or heap leach facility in accordance with

29 Section E3.1.3 of the standard review plan.” Following this sentence, state what information the 

30 applicant provided in the application, including identification of the information that was omitted 

31 or inadequate. As discussed in the introduction of this SRP, a bullet or sentence format may be 

32 used to list what information the applicant has provided. Next, state why a license condition is 

33 needed, followed by the license condition or conditions.

34

35 In a separate paragraph following the discussion of the required license condition(s), include the 

36 statement: “Based on the review conducted by NRC staff, the information provided in the 

37 application, supplemented by provisions of the license condition(s) discussed above, meets the 

38 applicable acceptance criteria of Section E3.1.3 of the standard review plan. Therefore, NRC

39 staff concludes that the applicant’s site benchmark dose implementation is acceptable and is in 

40 compliance with 10 CFR Part 40, Appendix A, Criterion 6(6), which describes requirements for 

41 site benchmark dose implementation.” If not discussed in the preceding paragraph, include a 

42 statement or summation as to why or how the application and license condition(s) jointly comply 

43 with the identified regulatory requirements.

44

45 C3.0 REFERENCES

46

47 Argonne National Laboratory. “Data Collection Handbook To Support Modeling the Impacts of 

48 Radioactive Material in Soil.” ANL/EAIS–8. Washington, DC: U.S. Department of Energy.

49 April 1993a.
Appendix C

C–11

1 –––––. “Manual for Implementing Residual Radioactive Material Guidelines Using RESRAD, 

2 Version 5.0.” ANL/EAD/LD–2. Washington, DC: U.S. Department of Energy. 

3 September 1993b.

4

5 Kennedy, Jr., W.E. and D.L. Strenge. NUREG/CR–5512, “Residual Radioactive Contamination 

6 from Decommissioning—User’s Manual.” Vol. 2. Washington, DC: NRC. April 2001.

7

8 NRC. NUREG–1727, “NMSS Decommissioning Standard Review Plan.” Washington, DC: 

9 NRC. July 2000.

10

11 Yu, C., A.J. Zielen, J.-J. Cheng, D.J. LePoire, E. Gnanapragasam, S. Kamboj, J. Arnish, 

12 A. Wallo II, W.A. Williams, and H. Peterson. “User’s Manual for RESRAD Version 6.” 

13 ANL/EAD–4. Argonne, Illinois: Argonne National Laboratory and Washington, DC: 

14 U.S. Department of Energy. July 2001.

APPENDIX D

GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT 

PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF 

LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL 

NUCLEAR MATERIAL

D–1

1 GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT 

2 PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF 

3 LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL 

NUCLEAR MATERIAL1 4

5

6

7

8 U.S. Nuclear Regulatory Commission

9 Division of Fuel Cycle Safety and Safeguards

10 Washington, DC 20555

11

12

13

14 April 1993

15

16

17 The instructions in this guide, in conjunction with Table D–1, specify the radionuclides and 

18 radiation exposure rate limits which should be used in decontamination and survey of surfaces 

19 or premises and equipment prior to abandonment or release for unrestricted use. The limits in 

20 Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which 

21 the radiological considerations pertinent to their use may be different. The release or such 

22 facilities or items from regulatory control is considered on a case-by-case basis.

23

24 1. The applicant shall make a reasonable effort to eliminate residual 

25 radioactive contamination.

26

27 2. Radioactivity on equipment or surfaces should not be covered by paint, plating, or other 

28 covering material unless contamination levels, as determined by a survey and 

29 documented, are below the limits specified in Table 1 prior to the application of the 

30 covering. A reasonable effort should be made to minimize the contamination prior to 

31 use of any covering.

32

33 3. The radioactivity on the interior surfaces of pipes, drain lines, or ductwork should be 

34 determined by making measurements at all traps, and other appropriate access points, 

35 provided that contamination at these locations is likely to be representative of 

36 contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of 

37 premises, equipment, or scrap which are likely to be contaminated but are of such size, 

38 construction, or location as to make the surface inaccessible for purposes of 

39 measurement shall be presumed to be contaminated in excess of the limits.

40

41 4. Upon request, the NRC may authorize an applicant to relinquish possession or control 

42 of premises, equipment, or scrap having surfaces contaminated with radioactive 

43 materials in excess of the limits specified. This may include, but would not be limited to, 

44 special circumstances such as razing of buildings, transfer of premises to another 

45

 1

NRC. “Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use of 

Termination of Licenses for ByProduct, Source, or Special Nuclear Material.” ML103620647. Washington, DC: U.S. 

Nuclear Regulatory Commission, Division o9f Fuel Cycle Safety and Safeguards. April 1993.
Appendix D

D–2

1

Table D–1. Acceptable Surface Contamination Levels

Nuclides* Average†‡§ Maximum†//§ Removable†¶§

U-nat, U-235, U-238 and 

associated decay products

5,000 dpm α/

100 cm2

15,000 dpm α /

100 cm2

1,000 dpm α /

100 cm2

Transuranics, Ra-226, 

Ra-228, Th-230, Th-228, 

Pa-231, Ac-227, I-126, I-129

100 dpm/100 cm2 300 dpm/100 cm2 20 dpm/100 cm2

Th-nat, Th-232, Sr-90, 

Ra-223, Ra-224, U-232, 

I-126, I-131, I-133

1,000 dpm/

100 cm2

3,000 dpm/100 cm2 200 dpm/100 cm2

Beta-gamma emitters 

(nuclides with decay modes 

other than alpha emission or 

spontaneous fission) 

except Sr-90 and others 

noted above.

5,000 dpm βγ/

100 cm2

15,000 dpm βγ/

100 cm2

1,000 dpm βγ/

100 cm2

*Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for 

alpha- and beta-gamma-emitting nuclides should apply independently.

†As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as 

determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and 

geometric factors associated with the instrumentation.

‡Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less 

surface area, the average should be derived for each such object.

§The average and maximum radiation levels associated with surface contamination resulting from beta-gamma 

emitters should not exceed 0.2 mrad/hr at 1 cm and 1.0 mrad/hr at 1 cm, respectively, measured through not more 

than 7 milligrams per square centimeter of total absorber.

//The maximum contamination level applies to an area of not more than 100 cm2

.

¶The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that 

area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive 

material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects 

of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should 

be wiped.

2

3 organization continuing work with radioactive materials, or conversion of facilities to a 

4 long-term storage or standby status. Such requests should:

5

6 a. Provide detailed, specific information describing the premises, equipment or 

7 scrap, radioactive contaminants, and the nature, extent, and degree of residual 

8 surface contamination.

9

10 b. Provide a detailed health and safety analysis which reflects that the residual 

11 amounts of materials on surface areas, together with other considerations such 

12 as prospective use of the premises, equipment, or scrap, are unlikely to result in 

13 an unreasonable risk to the health and safety of the public.

14

15 5. Prior to release of premises for unrestricted use, the applicant should make a 

16 comprehensive radiation survey which establishes that contamination is within the limits 

17 specified in Table D–1. A copy of the survey report should be filed with the Division of 
Appendix D

D–3

1 Fuel Cycle Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, 

2 DC 20555, and also the Administrator of the NRC Regional Office having jurisdiction. 

3 The report should be filed at least 30 days prior to the planned date of abandonment. 

4 The survey report should:

5

6 a. Identify the premises.

7

8 b. Show that reasonable effort has been made to eliminate residual contamination.

9

10 c. Describe the scope of the survey and general procedures followed.

11

12 d. State the findings of the survey in units specified in the instruction.

13

14 Following review of the report, the NRC will consider visiting the facilities to confirm the survey.

15

16

APPENDIX E

OUTLINE RECOMMENDED BY THE U.S. NUCLEAR REGULATORY 

COMMISSION STAFF FOR PREPARING SITE-SPECIFIC FACILITY 

RECLAMATION AND STABILIZATION COST ESTIMATES FOR REVIEW

E–1

1 OUTLINE RECOMMENDED BY THE U.S. NUCLEAR REGULATORY 

2 COMMISSION STAFF FOR PREPARING SITE-SPECIFIC FACILITY 

3 RECLAMATION AND STABILIZATION COST ESTIMATES FOR REVIEW

4

5 As required by Criteria 9 and 10 of 10 CFR Part 40, Appendix A, the licensee shall supply 

6 sufficient information for the U.S. Nuclear Regulatory Commission (NRC) to verify that the 

7 amount of coverage provided by the financial assurance will permit the completion of all 

8 decontamination, decommissioning, and reclamation of sites, structures, and equipment used in 

9 conjunction with byproduct material. Cost estimates for the following items (where applicable) 

10 must be submitted to NRC with the initial license application or reclamation plan, and must be 

11 updated annually, or as otherwise specified in the license. Cost estimates must be calculated 

12 on the basis of completion of all activities by a third party. Unit costs, calculations, references, 

13 assumptions, equipment and operator efficiencies, et cetera, must be provided. The annual 

14 surety estimate must be prospective of all work to be performed at the site. The licensee must 

15 provide estimated costs for all decommissioning, reclamation, and ground-water cleanup work 

16 remaining to be performed at the site, and should not simply deduct the cost of work already 

17 performed from the previous surety estimate [see NRC Generic Letter 97-03 (NRC, 1997)]. The 

18 licensee can propose a deduction for work done and approved by NRC as meeting 

19 specifications with its annual cost estimate. 

20

21 The detailed cost information necessary to verify the cost estimates for the preceding categories 

22 of closure work is summarized in the recommended outline that follows. For each area, 

23 estimates should include the costs for equipment; materials; labor and overhead; licenses, 

24 permits, and miscellaneous site-specific costs; and any other activity or resource that will 

25 require expenditure of funds.

26

27 (I) Facility Decommissioning

28

29 This includes dismantling and decontamination, or disposal of all structures and equipment. 

30 This work may be done in two phases. In the first phase, only the equipment not used for 

31 groundwater cleanup (including the stability monitoring period) is removed. Removal of the

32 remaining equipment would be performed in a second phase, after the approved completion 

33 of ground-water cleanup. The buildings may be decontaminated and released for 

34 unrestricted use.

35

36 (A) Salvageable building and equipment decontamination. For each building or 

37 piece of equipment listed, the following data should be provided:

38

39 (1) Area of contamination;

40

41 (2) Survey costs; and

42

43 (3) Decontamination costs.

44

45
Appendix E

E–2

1 (B) Non-salvageable building and equipment demolition and disposal:

2

3 (1) List of major categories of building and equipment to be disposed of and 

4 their corresponding quantities: 

5

6 (a) Structures (list each major structure), metric tons [tons(short)] of 

7 material, and building volume cubic meters (cubic yards);

8

9 (b) Foundation concrete [cubic meters (cubic yards)];

10

11 (c) Process equipment [metric tons (tons (short)];

12

13 (d) Piping and insulation (lump sum); and

14

15 (e) Electrical and instrumentation (lump sum).

16

17 (2) Disposal of chemical solutions within the facility.

18

19 (C) Cleanup of contaminated areas (ore storage pad, access roads, process area, 

20 evaporation pond residues, etc.)

21

22 Reclamation—This entails recontouring the tailings disposal cell and evaporation

23 ponds and placing top soil or other materials acceptable to NRC. Reclamation

24 may also include cleanup of windblown materials and revegetation, including, but 

25 not limited to:

26

27 (1) Cleanup of windblown materials (e.g., volume and area, unit

28 cost/cubic yard);

29

30 (2) Placement of borrow materials removal (e.g., rental rate, cost/cubic yard);

31

32 (3) Dust suppression and site maintenance;

33

34 (4) Monitoring and testing of construction;

35

36 (5) Regrading;

37

38 (6) Placement of the frost barrier;

39

40 (7) Placement of the radon barrier

41

42 (8) Installation of erosion protection and armor

43

44 (9) Installation of any vegetative cover;

45

46 (10) Design and construction of drainage ditches;

47
Appendix E

E–3

1 (11) Recontouring of land surfaces; and

2

3 (12) Revegetation.

4

5 (II) Ground-Water Cleanup and Well Decommissioning

6

7 Ground-water cleanup is done in accordance with an approved corrective action 

8 plan. The costs include water treatment equipment, operation, maintenance, and

9 component replacement.

10

11 (A) Method of cleanup;

12

13 (B) Volume of aquifer required to be restored, area and thickness of aquifer, number

14 of required pumping cycles, and cycling time;

15

16 (C) Verification sample analysis; and

17

18 (D) Well decommissioning:

19

20 (1) Number of drill holes to be plugged;

21

22 (2) Depth and size of each drill hole; and

23

24 (3) Material to be used for plugging including acquisition, transportation,

25 and plugging.

26

27 (III) Radiological Survey and Monitoring

28

29 Radiological Survey—Surveys and soil samples for radium in areas to be released for

30 restricted use. Soils around the tailings disposal cell, evaporation ponds, and process

31 buildings should be analyzed for radium content. A gamma survey of all areas should

32 be made before release for unrestricted use. All equipment released for unrestricted use 

33 should be surveyed and records maintained.

34

35 (A) Soil samples for radium (and uranium and thorium, if needed) (e.g., number, cost 

36 to collect, and analyze);

37

38 (B) Decommissioning equipment and building smear samples and alpha

39 surface surveys;

40

41 (C) Gamma survey frequency, location, and techniques (e.g., type, number,

42 unit cost);

43

44 (D) Environmental monitoring; and

45

46 (E) Personnel monitoring.

47

48
Appendix E

E–4

1 (IV) Project Management Costs and Miscellaneous

2

3 Itemize estimated costs associated with project management; engineering design,

4 review, and change; mobilization; legal expenses; power during reclamation; quality

5 control; radiological safety; and any costs not included in other estimation categories. 

6 Costs should include preparation of completion report and license termination activities.

7

8 Potential needs for future well maintenance or replacement are identified. If periodic

9 well replacement is projected, an increase in the long-term care payment is included

10 [ASTM Standard D 5978 (ASTM International, 2005)].

11

12 (V) Labor and Equipment Overhead, Contractor Profit

13

14 Overhead costs for labor and equipment and contractor profit may be calculated as

15 separate items or loaded into hourly rates. If included in hourly rates, the unit costs

16 must identify the percentages applied for each area.

17

18 (VI) Long-term Surveillance Fee

19

20 The fee required by 10 CFR Part 40, Appendix A, Criterion 10, to include cost of any

21 required long-term monitoring (e.g., ground water) or maintenance (e.g., fences,

22 vegetation control).

23

24 (VII) Contingency

25

26 The licensee should add a contingency amount to the total cost estimate for the final site 

27 closure. As of the date of this SRP, the staff currently considers a 15 percent 

28 contingency to be an acceptable minimum amount. The licensee should evaluate if the 

29 15 percent contingency recommendation has been revised by staff.

30

31 (VIII) Adjustments to Surety Amounts

32

33 The licensee is required by 10 CFR Part 40, Appendix A, Criterion 9, to adjust cost

34 estimates annually to account for inflation and changes in reclamation plans. The

35 submittal should be in the form of a request for amendment to the license.

36

37 (A) Adjustments for inflation: The licensee should submit a revised surety

38 incorporating adjustments to the cost estimates for inflation 90 days before 

39 each anniversary of the date on which the first reclamation plan and 

40 cost estimate was approved. The adjustment should be made using the 

41 inflation rule indicated by the change in the Urban Consumer Price Index 

42 published by the U.S. Department of Labor, Bureau of Labor Statistics.

43

44 (B) Changes in Plans:

45

46 (1) Changes in the process, such as size or method of operation;

47

48 (2) Licensee-initiated changes in reclamation plans or reclamation/

49 decommissioning activities performed;

50 (3) Adjustments to reclamation plans required by NRC; and

51
Appendix E

E–5

1 (4) Proposed revisions to reclamation plans must be thoroughly documented

2 and cost estimates and the basis for cost estimates must be detailed for

3 NRC review and approval.

4

5 To avoid unnecessary duplication and expense, NRC shall take into account surety

6 arrangements required by other federal agencies, state agencies, or other local governing

7 bodies. However, NRC is not required to accept such sureties if they are not sufficient. 

8 Similarly, no reduction to surety amounts established with other agencies shall be effected 

9 without NRC approval. Copies of all correspondence relating to the surety between the licensee 

10 and the state should be submitted to NRC. If authorized by NRC to maintain a surety with the 

11 state as the beneficiary, it is the responsibility of the licensee to give NRC verification of that 

12 surety; ensure that the agreement with the State specifically identifies the financial surety’s 

13 application, uranium mill tailings site, and decommissioning/reclamation requirements; and 

14 transfer the long-term surveillance and control fee to the U.S. Department of the Treasury 

15 before license termination.

16

17 All costs (unit and total) are to be estimated on the basis of third party independent contractor

18 costs (include overhead and profit in unit costs or as a percentage of the total). Equipment

19 owned by the licensee and the availability of licensee staff should not be considered in the

20 estimate to reduce cost calculations. All costs should be based on current-year dollars. Credit

21 for salvage value is generally not acceptable on the estimated costs.

22

23 NRC staff review may include a comparison of unit cost estimates with standard construction

24 cost guides (e.g., R.S. Means, Dodge Guide, Data Quest) and discussions with appropriate

25 state or local authorities (e.g., highway cost construction). The licensee should provide

26 supporting information or the basis for selection of the unit cost figures used in estimates. The

staff may elect to use a publicly available computer code such as RACERTM 27 (Talisman Partners,

28 Ltd., 2000) or spreadsheet to assess these costs.

29

30 References

31

32 ASTM International. D 5978, “Standard Guide for Maintenance and Rehabilitation of 

33 Ground-Water Monitoring Wells.” West Conshohocken, Pennsylvania: ASTM International. 

34 2005.

35

36 NRC. “Annual Financial Surety Update Requirements for Uranium Recovery Licensees.” 

37 Generic Letter 97-03. Washington, DC: NRC. July 1997.

38

Talisman Partners, Ltd. “Introduction to RACER 2000TM 39 (Version 2.1.0)—A Quick Reference.” 

40 Englewood, Colorado: Talisman Partners, Ltd. 2000.

APPENDIX F

U.S. NUCLEAR REGULATORY COMMISSION POLICY OF 

SAFETY CULTURE

F–1

1 U.S. NUCLEAR REGULATORY COMMISSION POLICY OF 

2 SAFETY CULTURE

3

4 Safety Culture

5

6 The safety culture policy statement was published in the Federal Register (76 FR 34773) on 

7 June 14, 2011, and can be found at http://www.gpo.gov/fdsys/pkg/FR-2011-06-14/pdf/2011-

8 14656.pdf. It is also posted in the U.S. Nuclear Regulatory Commission’s (NRC) Agencywide 

9 Documents Access and Management System (ADAMS) Accession Number ML11146A047.

10

11 Safety Culture Policy Statement

12

13 The purpose of this Statement of Policy is to set forth the Commission’s expectation that 

14 individuals and organizations establish and maintain a positive safety culture commensurate 

15 with the safety and security significance of their activities and the nature and complexity of their 

16 organizations and functions. This includes all licensees, certificate holders, permit holders, 

17 authorization holders, holders of quality assurance program approvals, vendors and suppliers of 

18 safety-related components, and applicants for a license, certificate, permit, authorization, or 

19 quality assurance program approval, subject to NRC authority. The Commission encourages 

20 the Agreement States, Agreement State licensees and other organizations interested in nuclear 

21 safety to support the development and maintenance of a positive safety culture, as articulated in 

22 this Statement of Policy.

23

24 Nuclear Safety Culture is defined as the core values and behaviors resulting from a collective 

25 commitment by leaders and individuals to emphasize safety over competing goals to ensure 

26 protection of people and the environment. Individuals and organizations performing regulated 

27 activities bear the primary responsibility for safety and security. The performance of individuals 

28 and organizations can be monitored and trended and, therefore, may be used to determine 

29 compliance with requirements and commitments and may serve as an indicator of possible 

30 problem areas in an organization’s safety culture. The NRC will not monitor or trend values. 

31 These will be the organization’s responsibility as part of its safety culture program. 

32

33 Organizations should ensure that personnel in the safety and security sectors have an 

34 appreciation for the importance of each, emphasizing the need for integration and balance to 

35 achieve both safety and security in their activities. Safety and security activities are closely 

36 intertwined. While many safety and security activities complement each other, there may be 

37 instances in which safety and security interests create competing goals. It is important that 

38 consideration of these activities be integrated so as not to diminish or adversely affect either; 

39 thus, mechanisms should be established to identify and resolve these differences. A safety 

40 culture that accomplishes this would include all nuclear safety and security issues associated 

41 with NRC regulated activities.

42

43 Experience has shown that certain personal and organizational traits are present in a positive 

44 safety culture. A trait, in this case, is a pattern of thinking, feeling, and behaving that 

45 emphasizes safety, particularly in goal conflict situations, e.g., production, schedule, and the 

46 cost of the effort versus safety. It should be noted that although the term ‘‘security’’ is not 

47 expressly included in the following traits, safety and security are the primary pillars of the NRC’s 

48
Appendix F

F–2

1 regulatory mission. Consequently, consideration of both safety and security issues, 

2 commensurate with their significance, is an underlying principle of this Statement of Policy. 

3

4 The following are traits of a positive safety culture:

5

6 (1) Leadership Safety Values and Actions—Leaders demonstrate a commitment to safety in 

7 their decisions and behaviors.

8

9 (2) Problem Identification and Resolution—Issues potentially impacting safety are promptly 

10 identified, fully evaluated, and promptly addressed and corrected commensurate with 

11 their significance.

12

13 (3) Personal Accountability—All individuals take personal responsibility for safety.

14

15 (4) Work Processes—The process of planning and controlling work activities is implemented 

16 so that safety is maintained.

17

18 (5) Continuous Learning—Opportunities to learn about ways to ensure safety are sought out 

19 and implemented.

20

21 (6) Environment for Raising Concerns—A safety conscious work environment is maintained 

22 where personnel feel free to raise safety concerns without fear of retaliation, intimidation, 

23 harassment, or discrimination.

24

25 (7) Effective Safety Communication—Communications maintain a focus on safety.

26

27 (8) Respectful Work Environment—Trust and respect permeate the organization.

28

29 (9) Questioning Attitude—Individuals avoid complacency and continuously challenge 

30 existing conditions and activities in order to identify discrepancies that might result in 

31 error or inappropriate action.

32

33 There may be traits not included in this Statement of Policy that are also important in a 

34 positive safety culture. It should be noted that these traits were not developed to be used for 

35 inspection purposes.

36

37 It is the Commission’s expectation that all individuals and organizations, performing or 

38 overseeing regulated activities involving nuclear materials, should take the necessary steps to 

39 promote a positive safety culture by fostering these traits as they apply to their organizational 

40 environments. The Commission recognizes the diversity of these organizations and 

41 acknowledges that some organizations have already spent significant time and resources in the 

42 development of a positive safety culture. The Commission will take this into consideration as 

43 the regulated community addresses the Statement of Policy.





UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, DC 20555-0001

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OFFICIAL BUSINESS
NUREG-2126 Standard Review Plan for Conventional Uranium Mill and Heap Leach Facilities